ML20010F651
| ML20010F651 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/26/1981 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML20010F650 | List: |
| References | |
| NUDOCS 8109110086 | |
| Download: ML20010F651 (475) | |
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MILLSTONE UNIT NO. 2 O EINIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT TABLE OF CONTENTS A. INTRODUCTION AND CHRONOIDGY B. EINIRONMENTAL SERVICE CONDITIONS
- 1. CONTAINMENT PROFILES, TEMPERATURES AND PRESSURE
- 2. RADIATION PROFILES i 3. SUBMERGENCE
- 4. HUMIDITY
- 5. CHEMICAL SPRAY
- 6. AGING - SURVEILLANCE AND PREVENTIVE MAINTENANCE PROGRAM
- 7. AREAS OUTSIDE CONTAINMENT
- 8. MARGIN
- 9. QUALITY ASSURANCE PROCEDURES C. COMPLIANCE WITH THE JUNE 30, 1982 DEADLINE
( D. RESPONSE TO APP 3NDIX D OF SER APPENDIX I -- MASTER LISTIhG O? ELECTRICAL COMPONENTS BY SYSTEM - NOT INCLUDED IN WIS SUBMITTAL; UNCHANGED FROM OCEBER 31, 1980 SUBMITIAL l t } APPENDIX II -- SYSTEM COMPONENT EVALUATION WORK SHEETS (SCEWS) AND JUSTIFICATIONS FOR CONTINUED OPERATION l l APPENDIX III -- RESPONSE TO AUDIT REPORT DATED CC'IDBER 14, 1980 - NOT INCLUDED IN THIS SUBMITTAL; UNCHANGED FROM OCTOBER 31, 1980 SUBMITTAL NOTE - Each of the three major sections of this submittal has its own unique listing of References. The reference nu.bers m used in the transmittal letter are distinct from the reference numbers used in the introduction and chronology section and Sections B and C O, of this submittal. The reference numbers used in the SCEWS and discrepant summary sheets (Agendix II) are distinct from either of the previous two segments. L
ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT MILLSTONE UNIT NO. 2 CHRONOLOGY AND REFERENCES o (1) February 8, 1979 .. .
. B. H. Grier letter to W. G. Counsil transmitting I&E Bulletin No. 79-01.
(2) March 23, 1979 . . . . . W. G. Counsil letter to R. W. Reid identifying unqualified SMLS. (3) April 6,1979 . . . . . . W. G. Counsil letter to R. W. Reid identifying qualified SMLS to be installed prior to Cycle 3 startup. (4) April 18, 1979 ... . . W. G. Counsil letter to R. W. Reid identifying unqualified solenoid operating valves will have qualified solenoids by Cycle 3 reartup. (5) May 8, 1979 . . . . . . G. Counsil letter to R. W. Reid identifying a
,.1LS on Valves S1-G14, G24, G34, and G44 will not be replaced; justification provided.
(6) June 6, 1979 .. ...
. B. it. Grier letter to W. G. Counsil transmitting I&E Bulletin No. 79-OlA, regarding ASCo solenoid valves.
( ]) (7) June 6, 1979 . .. . . . W. G. Counsil letter to N. C Mosely tracesitting response to I&E Bulletin No. 79-01. (8) September 4,1979 . . . . W. G. Counsil letter to N. C. Mosely transmitting additioral i>1ormation to response to I&E Bulletin No. 79-01, June 6, 1979 letter. (9) September 5, 1979 . . . . W. G. Counsil letter to R. W. Reid identifying unqualified RTD's in containment - continued operation jurtified. (10) September 19, 1979 . . . W. G. Counsil letter to R. W. Reid submitting followup report to September 5, 1979 letter. (11) January 9, 1980 . . . . . W. G. Counsil letter to B. H. Grier transmitting response to I&E Bulletin No. 79-28/ Defective Gaskets in NAMCO SMLS. (12) January 14, 1980 . . . . B. H. Grier letter to W. G. Counsil transmitting I&E Bulletin No. 79-01B.
. W. G. Counsil lett( ) N. C. Mosely transmitting (13) January 18, 1980 . . .
.! update to original I Bulletin No. 79-01 response
-- additional inform.cion.
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Envircom2ntal Qualificction cf Electrical Equipment Millstone Unit No. 2 (,- Page 2 (14) Februa ry 29, 1980 . . . B. H. Grier letter to W. G. Counsil transmitting j Supplement to I&E Bulletin No. 79-OlB. , ! (15) March 3, 1980 . . . . . W. G. Counsil letter to B. H. Grier transmitting response to Items 1 - 3 to I&E Bulletin No. 79-OlB. (16) March 31, 1980 . . . . . W. G. Counsil letter to B. H. Grier transmitting update to March 3,1980 letter, Items 1 - 3 of I&E Bulletin No. 79-01B. (17) April 17, 1980 . . . . . W. G. Counail letter to B. H. Grier transmitting update of original response to I&E Bulletin No. 79-OlB, March 3, 1980 letter. (18) May 23, 1980 . . . . . . Commission issue s Memorandum and Order requiring SER's by February 1, 1981 and tctal compliance by June 30, 1982. (19) July 14, 1980 . . . . . NNECO representatives attend Region I clarification meeting. (20) July 16, 1980 . . . . . V. G. Counsil letter to B. H. Grier update to original response to I&E Bulletin No. 79-03B, March 3,1990
~s letter, addressing commitments mad in the April 17, I(d 1980 letter.
(21) August 26, 1980 . . . .. R. T. Carlson letter to W. G. vounsil discussing audit findings on selected com: anents. (22) August 29, 1980 . . . . P A. Clerk letter to W. G. Counsil transmitting t,.c Order for Modification of License requiring a response by Novembar 1, 1980. (23) September 10, 1980 . . W. G. Counsil letter to B. Wolf e (GE) requesting expedited response regarding qualification documen-tation. I (24) September 19, 1980 . . . D. G. Eisenhut letter to W. G. Counsil transmitting Revised Order for Modification of License. (25) September 30, 1980 . . . NRC issues Supplement 2 to I&E Bulletin No. 79-OlB. (26) October 1, 1980 . . . . D. G. Eisenhut letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits requesting pertinent information relative '.c environmental qualification testing. l w - < m w --~ - ---.-..-m . .a a .:-
1 Environmental. Qualification of Electrical Equipment Millstone Unit No. 2 - Page 3 (27) October 9, 1980 . . .. . W. G. Counsil letter to J. Blachly (Siemans-Allis, () Incorporated) requesting expedited response regard-ing qualification documentation. , (28) October 14, 1980 . . . . R. T. Carlson letter to W. G. Counsil discussing findings of audit regarding comparison of qualif ica- , tion documentation to plant components. l (29) October 20, 1980 . . . NNECO representative responds to request of NRC ] Project Manager to provide status of the response to the Order, j (30) rvtober 24, 1980 . .. B.11. Crier letter to W. G. Counsil t ransmit t ing Supplement 3 to lie Bulletin No. 79-01B. i (31) October 24, 1980 . . . . R. A. Clark let. tor to W. G. Counsil transmitt ug
- an inmediately e f fective order regarding modifica-tions to the license end Technical Specifications.
4 i (32) October 31, 1980 .. . . W. G. Counsil letter to D. G. Eisenhut providing . j information, SCEW sheets, and qualification references,
- fufilling the requirements issued by the Order of Reference (22).
l (33) November 26, 1980 . . . . D. G. Eisenhut letter to W. G. Counsil, Generic ! Clarification of Documentation required which is } associated with Central Qualification file. () (34) December 4,1980 . . . . W. G. Counsil letter to 11. R. Denton requesting - a hearing on the Order issued by Reference (31). (35) January 16, 1981 . . . . D. G. Eisenhut letter to W. G. Counsil holding hearing request in abeyance. i (36) January 19, 1981 . . . . D. G. Eisenhut letter to All Licensees clarifying Bulletin 79-01B requirements. (37) January 20, 1981 . . . . W. G. Counsil letter to D. G. Eisenhut identifying the lack of planned Environmental Qualification i testing. (38) January 30, 1981 . . . . W. G. Counsil letter to D. G. Eisenhut concurring with 30 day holding of hearing request. (39) January 30, 1981 . . . . W. G. Counsil letter to D. G. Eisenhut updating October 31, 1980 submittal.
- (40) March 10, 1981 . . . . . D. G. Eisenhut to all plants; staff position that summary qualification reports not adequate.
; (41) April 14, 1981 . . . . . B. H. Grier to W. G. Counsil transmitting Circular 81-06; potential dificiencies in Foxboro trans-
- j. mitters.
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Environmental Qualification of Electrical Equipment Millstone Unit No. 2 Page 4
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(~~T l (42) April 14, 1981 . . . . . . T. M. Novak to W. C. Counsil; 10 day letter i requiring justification of continued operation in light of potential dificiencies. I (4 3) April 30, 1981 . . . . . . W. G. Counsil to T. M. Novak; providing justification for continued operation in 10-day response. (44) May 27, 1981 . . . .. . . R. A. Clark letter to M. C. Counsil; transmitting the SER, for review and 90 day response. (45) June 4, 1981 . . . . . . . W. G. Counsil to Hendrie requesting extension of June 30, 1982 deadline. (46) June 12, 1981 . . . . . . D. G. Eisenhut to W. G. Counsil allowing 90 days < for hearing request after date of issuance of SER. (47) June 22, 1981 . . . . . . Industry Petition for extension of deadline for compliance with CLI-80-21. l (48) June 26, 1981 . . . . . . W. G. Counsil letter to D. G. Eisenhut, commenting l on anticipated usefulness of July 7 - 10 meeting. ! (49) . 29, 1981 . . . . . . NRC response to industry petitions po.4tponing recommendation until July 31, 1981.
~) (50) July 16,1981 . . . .. . W. G. Counsil letter to H. R. Denton providing
{d / feedback on July 7 - 10 environmental qualifica-tion meeting. (51) July 31, 1981 . . . .. . Staff position to the Commission recommending one j year extension to the June 30, 1982 deadline. (52) August 14, 1981 . . . . . W. G. Counsil letter to D. G. Eisenhut documenting ' position on qualification of replacement parts. (53) August 14, 1981 . . .. . D. G. Eisenhut letter to W. G. Counsil proposing additional delay on affirmation or withdrawal of pending hearing requests. (54) August 20, 1981 . . . . . W. G. Counsil letter to D. C. Eisenhut, ac cep tir.g Staff proposal of Reference (53) regarding pending hearing requests. 1 t l [h 8 N] I
A. _ INTRODUCTION AND CHRONOLOGY Northeast Nuclear Energy Company (NNECO) was initially requested to address (( ) the issue of environmental qualification of electrical equipment for , Millstone Unit No. 2 in the form of a docketed response by Reference (1). In accordance with the provisions of item 4 of Ref erence (1), References (2) , through (5) were submitted to notify the Commission that certain stem-mounted limit switches were lacking the requisite qualifiestion, and identified corrective action and justification for continued operation. j By Reference (6), the NRC issued 1&E Bulletin No. 79-OLA, regarding ASCo
- solenoid valves. NNECO's initial response to the provisions of items 1 through 3 of Ref erence (1) was docketed by Reference (7) and supplemented by Ref erence (8) . Ref erences (9) and (10) were submitted in conformanca with item 4 of Reference (1) and discussed the qualification status of
' resistance temperature detectors used to monitor containment air temperaturas.
Justification for continued operation was provided. Reference (11)'docketel a response to 1&E Bulletin No. 79-28 regarding NAMCo stem-mounted limited switches. The issue of environmental qualification was escalated to a higher priority status upon issuance of Reference (12). An indication of the magnitude of this task can be obtained b3 reviewing the attached chronology. It is important to recognize that NNECO resources have been strained significantly, not merely because of the amount of equipment requiring qualification j documentation, but also because of the numerous changes and conflicts in NRC guidance documents on this subject. To support this position, the attached chronology is discussed to specify instances where such conflicts have arisen
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'" and to identify the applicability of these reference documents as of this l
writing. l Supplemental information in the form of System Component Evaluation Work Sheets (SCEUS) was provided in Reference (13). For each component, i inf ormation in the form of component description, description of the accident environment, the environment to which the equipment is qualified, the manner of qualification, and the identification of the specific supporting qualifica-tion documentation was provided. Resolution of the issues identified in Reference (6) was also provided by Reference (13). The firot supplement to Ref erence (1) was issued by Reference (14). The supplemental information was presented in the form of seventeen (17) generic questions and answers. Of particular significance was the response to j Question 5, in which the Staff stated that TM1 lessons-learned equipment was not to be addressed. The response to Question 9 is also of significance as the Staf f states that the requirements and positions in NUREG-0588 are the same as those in NUREG-0578 in relation to environmental qualification of electrical equipment and components. The response to Question 18 of l Reference (25) discusses the differences between NUREG-0588 and NUREG-0578 regarding the calculation of radiation source terms. 1 i I
By Ref erences (15), (16), and (17), NNECO responded to the specific provisions of Reference (12). The equipment qualification status, which is superseded . by the docketing of Appendix II to this report, was presented to the extent it was available at that time. Reference (15) provided inforr.ation regarding ' the radiation service conditions and temperature and pressure profiles which remain applicable as shown in Appendix 11. In Ref erence (18), the Commissioners issued the Memorandum and Order, and required the NRC Staf f to issue Saf ety Evaluation Reports by February 1,1981. It is NNECO's intention that the report will be the foundation for a f avorable SER. During the regional meetings on this subject (Reference (19)), additional changes in NRC requirements or new interpretations were provided. The Staff explained that there was no lenger a need to address areas of the plant which remain at ambient conditions. The Staff also discussed the various qualification methods which are acceptable, and these included evaluation, analysis, and similarity considerations. Subsequent to the meeting, NNECO endeavored to restructure the program to respond to the new guidance. By Reference (20), supplemental information to Reference (17) was provided. Coc=itments made in Ref erence (17) were fulfilled or new schedules were established. The results of a corporate office audit conducted by the Office of Inspection and Enforcement were documented in Ref erence (21). No items of non-compliance were identified during the 16-hour verification inspection. In Ref erence (22), the Staf f issued the Order for Modification of License and required a response by November 1, 1980. Although eventually superseded by Reference (24), the principle purpose of this report is to respond to Reference (22). NNECO has encountered numerous difficulties in obtaining some of the necessary qualification documentation. Several vendors are no longer in business supplying components for nuclear applications, others are no longer in existence, and still others express great reluctance in providing the requested data. Postulated reasons include difficulties in retrieval or commercial considerations. In attempting to deal with this dilemma, NNECO has resorted to letters such as References (23) and (27) to expedite receipt of the necessary information. Although such efforts have been helpful, they have not resolved a remaining dif ficulty in obtaining the required qualification documentation. In Reference (25), the Staff clarified its position on a number of require-ments and escalated the scope of the review ef fort significantly. NNECO's exceptions and positions with cespect to the requirements of this document were dis-ussed in the forwarding letter. NNECO reemphasizes that extreme difficulties are encountered when the NRC issues documents which revise the scope of a major effort which are required by order to be submitted merely one month from the issuance of Reference (25).
(() By Ref erence (26), the Staf f requested pertinent information regarding environ-mental qualification tests to be conducted within the next two years. We are endeavoring to supply the requested information, but did not receive this document until Tuesday, October 14, 1980. The current work load on individuals involved in environmental qualification will likely preclude a complete response by November 1,1980, but NNECO intends to respond . as soon as possible. No plans for qualification testing for NNECO have been ' identified as of this writing. Reference (28) documents the results of a site audit conducted by the Office I of Inspection and Enforcement. No itema of non-compliance were identified. ; A response is provided as Appendix 111 to this report. ; I Reference (29) identifies a call between NNECO representatives and the i NRC Project Manager for Millstone Unit No. 2 regarding the status of the response to the Order. The questions posed were suggestive of potential for changes / relaxations in certain portions of MRC requirements. The responses provided by NNECO are intended to demonstrate its continued position that the purpose of this effort is to demonstrate the adequacy of the current qualification status of safety-related electrical equipment, which is possible even if certain provisions of the qualification requirements cannot be ful- l e filled by documentation, a - Ry Ref erence (30), the Staff transmitted Supplement 3 to 1&E Bulletin No. 79-OlB. This document delayed the schedule for submittal of all qualification documentation regarding TMI Action Plan equipment until February 1, 1981. {} Similarly, the qualification information for equipment required to achieve and maintain a cold shutdown condition is not required until February '.,1981. NNECO's position regarding these changes is being [ provided now and will be supplemented by February 1, 1981. l i By Reference (31), NNECO received an immediately effective Order which modified the license and the Technical Specifications. June 30, 1982 has been established in the license as the date by which fully qualified safety-related electrical equipment must be installed. By December 1,1980, NNECO must establish complete and auditable records and amintain them at central locations. Steps are being taken to comply vita these requirements nr. schedule. By Reference (32) NNECO provided information requested in Reference (24), , consisting of qualification information for safety-related electrical j equipment in accordance with the Commission's guidance in this matter. l Where total qualification was not incorporated into this report , jus- 1 l tification for continued operation until total conformance could be l achieved was provided. i
! In Reference (33), D. G. Eisenhut addressed clarification of the !
October 24, 1980 Orders to all Licensees. The provision of the Orders requiring centrally located records did not call for creation of any recrods, per se, but the existance of a system which contained a complete set of documentation on Environmental Qualification. Reference (34) requested that a hearing be held to determine the validity of NUREG-0588 requirements, specifically the requirement of meeting the June 30, 1982 deadline for qualification of all safety-related electrical equipment.
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l () In Reference (35), D. G. Eisenhut informed W. C. Counsil that the Commission intended to hold the Reference (34) hearing request in abeyance until 30 l days af ter the issuance of the SERs for our facilities, thus, providing the l option of reviewing the Safety Evaluations while still preserving our ti ability to seek a hearing. A response regarding the acceptability i. of this approach was requested by January 30, 1981. Ref.erence (36), from D. G. Eisenhut to all Licensees, provided information in response to licensee requests regarding certain requirements of Bulletin 79-01B, the Reference (18) memorandum, and the Reference (30) Order. In Reference (37), W. G. Counsil informed D. G. Eisenhut that there are no plans for environmental qualification testing that are applicable to Millstone Unit No. 2. Reference (38) forwarded W. G. Counsil's acceptance of D. G. Eisenhut's proposal to hold our hearing request in abeyance for 30 days following_the issuance of the Safety Evaluations for our facilities with the qualification that the 30 days be counted as after the receipt of the last of the Safety Evaluaticn Reports for the three operating units in the NU System. Reference (39) updated the Reference (32) submittal, providing updated SCEW sheets, a revised index listing all safety-related electrical equipment, and additional or replacement pages for the Master Listing of Electrical Components. This submittal focused on equipment required exclusively () to achieve cold shutdown, but did not totally reflect the Staff guidance contained in Reference (36). Reference (40) forwarded D. G. Eisenhut's letter to all licensees, clari-fying the NRC Staff requirements for a detailed explanation of test pro-cedures and the results thereof. These detailed reports on Environmental Qualification of Class lE Electrical Equipment would be then considered ! proprietary. Reference (41) Circular 81-06) contained information on certain Foxboro .
- 10-to-50 Mil 11 ampere Transmitters. Licensees were advised of the improper I use of Teflon wire insulation and an unsuitable capacitor in the amplifier section of these transmitters.
In Reference (42), T. M. Novak transmitted the preliminary results of the ! Staff review of environmental qualification of safety-related electrical equipment at Millstone Unit No. 2. The Staff review resulted in the alleged 2 identification of a number of potential dificiencies such that conformance to DOE guidelines could not be demonstrated. NNECO was required to respond within ten days, providing justification for continued operation in light 4 of these alleged deficiencies.
- Ref erence (43), W. G. Counsil provided the required justification for 4
continued operation, pointing out a number of specific concerns with the a content of Reference (42) . NNECO suggested that the current status of the Staff's SER did not accurately reflect the qualification status of electrical equipment at Millstone Unit No. 2 and that the subject concerns should be evaluated in detail prior to the issuance of the final SER. l
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Reference (44) transmitted the Scfety Evaluation Report (SER). The NRC r3 Staff identified the information required, and the actions necessary ( ,) _ to comply with Reference (31). NNECO was given the option of presenting alternatives to staff positions, however, all information was requested to be provided within 90 days. NNECO has encountered difficulties in discerning the bases for the alleged deficiencies in many instances. In Reference (45), W. G. Counsil informed Dr. J. Hendrie of the substantial amounts of manpower and resources al ready expended on environmental qualifi-cations, and that licensee evaluations found the NRC Staff requirements for a June 30, 1982 deadline for full compliance neither appropriate, realistic, nor attainable. NNECO requested relief from the June 30, 1982 deadline, in the form of extensions to a minimum of seventeen months af ter SER issuance. Other issues mentioned were equipment in mild environments, replacement parts, aging requirements, and containment profiles. This document was subsequently appended to Reference (49) . l In Reference ( 46) , D. G. Eisenhut informed W. G. Counsil of the Staff's ' decision to extend the 30-day abeyance period granted in Reference (34) to 90 days. Within 90 days of the issuance of the SER for Millstone Unit No. ?, NNECO was requested to inform the Staff of its intentions regarding the hearing request of Reference ( 34), and of the specific issues to be raised in that proceeding. In Reference ( 4 7) , the law firm of Debevoise and Liberman filed a petition on behalf of 20 licensees seeking a thirteen month extension of the June 30, 1982 deadline established by CLI-80-21. The petition stated that few, if j p_s s i any, licensees could meet the deadline, and that the assumptions upon which CLI-80-21 was based have proven to be significantly understated in ter. .s of the length of time needed for compliance. Reference ( 48) informed the Staff that NNECO planned to have representatives present at the July 7 - 10, 1981 meeting on envirenmental qualification. Based upon speculation regarding the results of the meeting, NNECO also intended to propose dates for licensee-specific meetings on this issue. l l Reference (49) informed the 20 petitioning licensees that the NRC Staff intended to postpone its decision on the Reference (47) petition until after the July 7 - 10 meeting. NNECO had no objection to this course of action. Reference (50) provided feedback on the July 7 - 10, 1981 meeting on environmental qualification. NNECO had a total of seven representatives in attendance at this meeting. While the meeting was of some benefit, additional dialogue on a plant-specific basis was determined to be necessary to re-solve the numerous remaining questions. Specific comments on the meeting were provided as an attachment. General comments regarding resource expendi-tures, adequacy and correctness of the SER, discrepancies between the SER and the TER, mild environments, and the June 30, 1982 deadline were also nrovided. A i i
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i 1 { In Reference (51), the NRC Staff responded to the Reference (47) petition, O recommending a one-year extension of the deadline to the Commission. Other
~
options were discussed, but a one year extension was recommended. Additional extensions of time could be authorized by the Director, Division of Licensing, on a case-by-case basis for good cause shown.
- Reference (52) established a written position on qualification of replace-i ment parts to the provisions of NUREG-0588. NNECO stated that " sound i reasons" for use of equipment lacking full qualification existed in numerous instances, and that such reasons are documented in the central qualification file.
Reference (53) forwarded D. G. Eisenhut's letter to W. G. Counsil proposing an additional delay in the Reference (37) hearing request, to allow NNECO to i consider-all recent or imminent developments. The Staff expressed its inten-tion to continue to pursue resolution of disputed technical issues. l In Reference (54), NNECO concurred with the Reference (53) proposal, agreeing to inform the Staf f of NNECO's decision on the hearing request within 30 days of Commission disposition of the industry petition. I O : t i ! i l l 4 i 1 i l
4 B.1 CONTAIIIMENT PROFILES, TEMPERATURE AND PRESSURE The information presented.in Reference (32) is duplicated below:
"The design basis temperature and pressure conditions for t
Millstone Unit No. 2 results from a postulated LOCA. The MSLB accident was also evaluated and although a comparable peak value was calculated, the duration of the transient was found to be shorter and the LOCA remains limiting. The profiles utilized in the qualification effort were based upon FSAR analyses, have been provided in earlier revisions of this report, and are presented in Appendix II. The analytical methodology employed to develop these pro-files is consistent with amplicable NRC requirements." In Reference (42), the Staff alleged that insufficient information was provided to substantiate the validity of the values specified. NNECO has subsequently been informed that the basis for the Staff position was that the values utilized did not satisfy the Staff's
" screening criteria", as defined in the July 7 - 10 meeting. .
NNECO responded to these alleged deficiencies in Reference (43). Although Reference (43) was docketed approximately one month
; prior to the issuance of Reference (44), Reference (44) is identical in content to Reference (42) with respect to temperature and pressure inside containment. This suggests to NNECO that the Staff either n failed to review or failed to understand Reference (43). Reference ty,) (43) continues to constitute NNECO's response and reiterates that 2790 F and 51.7 psig remain the qualification limits. The methods used to arrive at these results are in full conformance with the provisions of NUREC-0588 and DPR-65.
i
B.2 ENVIRONMENTS - RADIATION PROFILES O The information presented in Reference (32) is duplicated below:
"By letter dated December 31, 1979, Northeast Nuclear Energy Company (NNECO) docketed the results of cal-celations performed to ascertain the radiation service conditions resulting from a design basis accident.
The methodology employed was consistent with the criteria promulgated by the NRC in NUREG-0578, and is thoroughly discussed in the December 31, 1979 submittal. Results for the 40-year normal operating dose, the LOCA dose, and the total dose were presented. These results remain applicable and are listed on the System Component Evaluation Work Sheets (SCEWS) of Appendix II as appropriate." In Reference (42), the Staf f requested additional information to justify the use of values less than the Staff's " screening criteria." NNECO submitted in Reference (43) a detailed and comprehensive response including the bases, assumptions, calculations, and results to substantiate the validity of the values utilized in the qualification process. It was noted there that the Reference (42) criterion for equipment inside containment was more severe than the values spceified in the DOR Guidelines or NUREG-0588. I Despite the level of detail provided in Reference (43) , the Staff did not even acknowledge receipt of this material in Reference (44). Inasmuch as the methodology utilized to calculate radiation service i conditions is in full conformance to the DOR Guidelines, NNECO concludes that the Reference (43) information constitutes a sat-isfactory response to Reference (44). If the Staff disagrees with this conclusion, we request that the Staff first review Reference (43) before rendering its views in the supplemental SER. I O i - - _ -
B.3 ENVIRONMENTS - SUBMERGENCE The information presented in Reference (32) in duplicated below:
"In previous docketed correspondence submitted in response to I&E Bulletin No. 79-01, as amended and supplemented, the appropriate submergence value for Millstone Unit No. 2 was identified and utilized. A conservative rep-resentation of the maximum inventory which could result from a LOCA was identified to be 88,000 cubic feet. This corresponds to a depth of water of 8.1 feet above the containment floor. This value is utilized as appropriate on the System Component Evaluation Work Sheets (SCEWS) in Appendix II."
The Staff concerns identified in Reference (44) are identical to those contained in Reference (42). Again, NNECO's detailed response was provided in Reference (43) and the Staff apparently failed either to review or understand NNECO's response. NNECO reiterates the following significant points of Reference (43): o Submergence levels insid2 containment were determined using j very conservative assumptions. o Reference (30) states that " qualification documentation for TMI Action Plan equipment not yet installed which does not require pre-implementation review should be submitted to C-)g NRC for review by the implementation date." Thus it is in-consistent with Reference (30) and misleading to require NNECO "to supplement the information presented and justify the adequacy of the design on an interim basis", prior to the due date for submittal of any documentation associated 91th this TMI Action Plan item. o The potential for submergence outside containment was thoroughly evaluated in the FSAR and summarized in Reference (43). NNECO concludes that the Reference (43) info rmation is responsive to the Staff concerns. 4
B.4 ENVIRONMENTS - HUMIDITY, INSIDE CONTAINMENT The information in Reference (32) is duplicated below: 4 j "The relative humidity of the air surrounding the 1 Category 1 equipment has been conservatively assumed to be 1007. for the duration of the elevated
. temperature and pressure condition resulting from
) a LOCA or a HELB unless otherwise noted in the l System Component Evaluation W'o rk Sheets (SCEWS) in j Appendix II. Additionally, it is assumed that d the entire ccmpartment associated with HELB ! instantly saturates with steam, even though the j Category 1 equipment may be separated by long dis-j tances and torturous pathways from the HELB. This i approach assures that an appropriate level of con-servatism has been employed in this evaluation." i The Staf f did not identify any concern with this approach. .C) i 1 4 l 1 i O-t
..,-,-~n --,.,,,-,,,n---._n-,,-,,-,--,--.,--,~, .-,.-,,-,,nem--. ,,,---r.---,-,,,n, , , - c.r----~, , . , , , , , - , - - ,,n ,,,,~w-a..,------r----,-
B.5 ENVIRONMENTS - CllEMICAL SPRAY The intormation presented in Reference (32) is duplicated below: () " Equipment subject to harsh chemical environments due to actuation of the containment spray system is identi-fled on the System Component Evaluation Work Sheets (SCEWS) . The operation of this system is detailed in the Millstone Unit No. 2 FSAR, Section 6.4. The composition of the spray is less than 2400 ppm boron as derived from the Refueling Water Storage Tank." The Staf f concluded this approach was acceptable in References (42) and (44), t v O)n
B.6 EtNIRONMENTS - AGING - SURVEILLANCE AND PREVENTIVE MAINTENANCE PROGRAMS ()
' The information presented in Reference (32) is duplicated below:
" Equipment which is subjected to harsh environments caused by a LOCA or High Energy Line Breaks (HELB) and which must operate to mitigate the consequences of those accidents is required to be environmentally qualified. Part of this qualification requires that the equipment be shown to operate successfully in an end-of-life condition.
To address this question, NUSCO has retained Wyle Laboratories to perform aging analysis for components which fall into this category. Normal radiation and temperature data were obtained from plant operating records and from in-service surveys conducted during the summer of 1980. Operating tem-perature surveys were performed during the hottest days of 1980 in the areas surrounding the Category I equipment and this information represents the Normal Maximum Temperature that the equipment would be sub-jected to thrcughout its design life. Additional conservatism was added in the aging assalysis by assuming that the equipment would be exposed con-tinually to these temperatures, giving no credit to seasonal and operational diff_rences in ambient (V~g temperatures. Identification of age sensitiv? components within the equipment is made increasingly more difficult with increasing age of the equipment. Although the analysis is not yet complete, there remains a high degree of confidence that the results will yield a satisfactory qualified life for components identified I in the System Component Evaluation Work Sheets (SCEWS). In conformance with the Commission's May 23, 1980 1 Order, NUSCO has committed to a program of replacement, I where this information is determined to be lacking. Additionally, justification for continued operation is included to provide the Staff full and complete information in accordance with the Order." Since the docketing of Reference (32), significant progress has l been made towards resolution of the aging question and updates to l individual SCEWS are included in Appendix II as a result of data obtained from our consultant, Wyle Laboratories, and other sources. In response to the verbal Staf f guidance at the July 7 - 10 meetings, we have summarized below NNECO's Surveillance and Preventive Maintenance Program which addresses safety-related electrical equip-ment in harsh environments. In conjunction with the data on in-( - dividual components indicated on the SCEW Sheets which describe 1 J the methodology used to determine expected life, NNECO concludes that the attached program fully complies with NRC requirements, as clarified by the Staff.
i MILLSTONE UNIT NO. 2 PREVENTIVE MAINTENANCE PROGRAM ELECTRICAL, INSTRUMENTATION AND CONTROL EQUIPMENT l The responsibility for Maintenance of Electrical, Instrumentation and Control Equipment is split among 3 entities at Millstone Unit 2. They are the Maintenance Department. Instrumentation and Control Department and the Produ tion Test Department. For those equipments which are committed to be periodically maintsined in the Safety Technical Specifications, an additional group, the Quality Control Department, has the responsibility to insure that the work is accomplished by the proper entity. For any given equipment type, a lead discipline is assigned and support is requested of the remaining groups as required in the maintenance of that device. There is also an In-Service Inspection Team at Millstone Unit 2, which is responsible for the operability of mechanical devices such as, valves, pumps and piping. The drivers fer the valves and pumps are not in this group's jurisdiction. However, should the tolerance of the mechanical device be exceeded, it may well be a problem with the Electrical Instrumentation and Control equipment. In that case the proper maintenance group would be called for assistance. RESPONSIBILITIES s 1. The Unit 2 Maintenance and Instrument and Control Supervisors are responsible for ensuring that equipment assig*.ed to their department is maintained, calibrated and tested to insure continued operabili f.
- 2. The NUSCO Production Test Field Supervisor is responsible for ensuring that equipment assigned to the NUSCO Production Test Department is maintained, calibrated and tested to insure continued operability.
- 3. The Unit 2 Superintendent is responsible for resolving any differences and making appropriate assignments to insure that the Unit electrical equipment is maintained, calibrated and tested to insure continued operability.
The following table defines the area of responsibility for the Maintenance, Instrumetation and Control and Production Test Departments. ITjy LEAD RESPONSIBILITY
- 1. Generators (Main and Diesel) Production Test
- 2. Motor Testing (all motors up to 7KV) Maintenance
- 3. Proteccive Relay Calibration and Production Test Trip Jesting A
V
i i l ITEM LEAD RESPONSIBILITY l 4. Transformer Testing
- a. Inside Transformers Maintenance I b. Outside Transformers Production Test l 5. Emergency Power Systems - Includes DG Maintenance j Electrical Controls, Batt. Chargers i
- 6. Plant Power Metering Calibration Production Test
] l 7. Transducer Calibration Production Test l 8. 480/120/125 volt switchgear Maintenance
- 9. Batteries Maintenance I
- 10. Main Generator Excitation and Production Test
- Voltage Regulator i 11. Electrical Testing of Modification
- a. NUSCO Projects Production Test
- b. NNECO Projects Mainterance
, 12. CEDM System
- (:) a. MG Set Motor and Generator Maintenance i,
; b. MG Set Control Cabinet including Production Test i
Protection, Starter and Regulator ! c. Trip Switchgear Cubicles / Busses / Breakers Maintenance
- d. Trip Switchgear Protection, Relaying and Production Test Wiring from RPS to Switchgear to i Breakers
- e. RPS Cabinets and Sensors Instrumentation & Controls
- 13. Pressurizer Heater Proportional Controllers Maintenance
- 14. Vital Power Systems; Computer Power Supply Maintenance and Inverters / Static Switches
- 15. Refueling Equipment Maintenance 16, 4 KV/7 RV Switchgear Maintenance l a. Breakers /Buswork Maintenance
(} b. Control / Protection on Feeders / Ties Production Test ( - 1 ! .2 - i
MAINTENANCE D2PARIMENT The Maintenance Department has a computerized listing of all the equipment for which they have lead responsibility. This listing includes the equipment number, preventive maintenance procedure reference, frequency of preventive maintenance, schedule for the preventive maintenance and defini-tion of type of preventive maintenance to be performed. INSTRUMENTATION AND CONTROL DEPARTMENT The Millstone Unit 2 Instrumentation and Controls Department utilizes the computer run developed by the architect engineer (MS-60) in conjunction with a manual filing system to assure all preventive maintenance and calibration is performed on schedule. PRODUCTION TEST The Production Test Department maintains a file on all of the equipment for which they have lead responsibility. Each equipment type has an approved procedure for maintenance and calibration of that device. REPLACEMENT OF THE MS-60 LISTING A new computerized listing is in the process of being developed for the Instrumentation and Control Department. It will be an interactive program which will allow the engineers and technicians to sort the list by any s one of a number of parameters. Provisions are being made for inclusion
/ of Preventive Maintenance and Environmental Qualification information.
Once operational, the crea*3m may be used by Maintenance and Production Test to encode the'. records. INCORPORATION OF ENVIRONMENTAL QUALIFICATION INFORMATION The July 7 - 10, 1981 meeting with the NRC Staff revised our understanding of the term " Qualified Life". IE Bulletin 79-OlB required NNECO to determine the
" Qualified Life" for each equipment item which is required to function in a harsh environment. This information is presented on the system component evaluation work sheet. Prior to the meeting it was understood that where qualified life exceeded plant life no specific maintenance was to be required for equipment environmental qualification. Subsequently the Staff verbally reque< ed NNECO to include all harsh environment equipment in their surveillance and maintenance programs to verify calculations and/or detect unexpected age related degradations. This is due to the technical uncertainties that exist in the scienti'ic community regarding prediction of aging mechanisms.
Table 1 lists the Generic Equipcent Items at Millstone Unit 2 which will be included in this program. Included in the Table is the surveillance required and the schedule for each preventive maintenance item. The majority of the surveillance and preventivt mainter:ance which is done on this equipment is currently performed on a periodic basis. However, f- there are a few items, such as terminal blocks, where new surveillances will (_g) be added to the procedures to address these unknown aging mechanisms.
For equipment items which contain numerous samples in similar normal () environments, such as cable, penetrations and terminal blocks, representative samples will be tested on a periodic basis, t
- The Surveillance and Preventive Maintenance Procedures contain visual inspectiona, where applicable, to observe any indications of postulated aging degradations. In those equipment where accelerated pre-aging was included in the harsh environment testing program, such as with cable and splices, visual inspection may be the only surveillance performed on a regular basis.
A program to ensure that data are available for trending and data are collected for all Harsh Environment Equipment will be in full force by ' June 30, 1982. i 9 q I (
Dockst 50-336 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT O MILLSTONE UNIT 2 TABLE 1 SURVEILLANCE AND PREVENTIVE MAINTENANCE OF EQUIPMENT LOCATE 9 IN A HARSH ENVIRONMENT (TESTS WHICH VERIFY AGING ANALYSIS) Generic Equipment Surveillance Period (Preventive Maintenance) 4 KV Motors IR Test Each refueling Hi-Pot Test Each refueling 480 volt Motors IR Test Each refueling Motor Operators (MOV's) IR Test See Note 1 Operation Time See Note 2 Solenoid Valves Qualifird SV's are replaced well Three (3) years s before they reach their qualified life. Inspections of replaced SV's IR, minimum pickup voltage and maximum drop out voltage will verify assumptions used in aging anaylsis. Limit Switches Visual Inspection Two (2) years Replace gaskets Two (2) years Cable and Terminations 4 KV Power IR Test Each refueling Hi-Pot Test Each refueling Cable and Terminations LV Power Visual Inspection Ten (10) years Control Instrumentation a Penetrations Leak Rate Each Refueling IR Test Ten (10) years Misc. Terminations IC Test Ten (10) years (See Note 5) Visual Inspection Ten (10) years Hydrogen Recombiner IR Test See Note 4 Rated Power Test _ _ . _ - . . _ . . _ _ . . _ _ , _ _ -~ . _
Env. Qual. of tinctrical Equipment Millstons Unit 2 Docket 50-336 Tsble 1 Page 2 l'\ j \s / Surveillance Generic Equipment (Preventive Maintenance) Period Instrumentation Transmitters Calibration Runs Each Refueling Radiation Detector Accellerometer Pre-Amp Pressure Switches RTD's NOTES Note 1 g A rolling schedule will be maintained such that c_2 MOVs are fully inspected at least once every five (5) years. Note 2 () Valve stroke time is verified in the in-service inspection program and not necessarily done during refueling outage. Note 3 IR test of terminations may be done as part of overall system test. Note 4 These tests are conducted as part of the surveillance requirements contained in the Safety Technical Specifications, Specification 4.6.4.2. They are performed during each refueling outage. Note 5 For termination systems where accelerated aging was not included as part of the harsh environment test program, IR Testing will be incorporated into the surveillance procedure. O
B.7 AREAS OUTSIDE CONTAINMENT f-~3 The information presented in Reference (32) is duplicCced below: O "The design basis temperature and pressure conditions for areas outside containment were provided in earlier revisions of this report and are presented in Appendix II. FSAR analyses, as amended, served as the basis for the calculation of the temperature and pressure environments." In Section 3.4 of References (42) and (44), the Staf f concluded that the temperature, pressure, and humidity parameters previously specified are acceptable. The submergence parameter was addressed in Section B.3. O i
B.8 HARGIN () on several occasion; during the course of the July 7 - 10 meeting, the Staf f raised questions and concerns regarding the adequacy of the margin available for the various parameters involved in the qualification process. To supplement the information provided in this report, NNECO's general treatment of the margin question is summarized as follows. For the vast majority of parameters and components evaluated, there exists a substantial margin between the minimum acceptable value based upon a plant-specific evaluation and the qualified value of the component in question. Availability of this margin is typical of many aspects of plant design and operation, and io indicative of the conservatism available in the design of the facility. Further, NNECO notes that the methodology utilized to develop the minimum acceptable qualification parameter limits includes sufficient conservatism to obviate further arbitrary conservatism. The methodology used is quite distinct from the technique of calculating a best-estimate value, in which case it would be appropriate to add some arbitrary conservatism to the final result of this calculation. The details of the methods used are presented in these sections of this report which address the individual qualification parameters. Examples of this concept include: o Submergence - The calculation included the entire inventory Ci of all credible water sources available on-site, o Radiation - A source term representative of an extremely degraded core, as specified in the DOR Guidelines, was assumed. o Chemical Spray - The maximum available boric acid concen-tration, some 680 ppm higher than the Technical Specification minimum value for the RWST, was assumed. NNECO therefore concludes that it is not necessary to impose additional margin beyond the conservatively calculated qualification values to assure that safety-related electrical equipment will perform its design function when exposed to a harsh environment.
i i B.9 QUALITY ASSURANCE PROCEDURES Northeast Utilities Service Company (NUSCO) provides Northeast Nuclear
! Energy Company (NNECO) with the necessary engineering support as described in the Northeast Utilities Nuclear Engineering and Operations Policies and Procedures Manual. The overall assurance of quality is directed by the Northeast Utilities Quality Assurance Program (NU-QAP).
j The NU-QAP topical report, Revision 3 meets the criteria in Appendix B to 10 CFR 50 and has been accepted by the NRC in the W. P. Haass letter to W. G. Counsil dated March 13, 1979, NRC Topical Report Evaluation. The environe. ental qualification effort which was accelerated with the issuance of IE Bulletin 79-01B and subsequently the Memorandum and i Order CLI-80-21, necessitated the re-review of qualification documenta-tion for all electrical equipment required to operate in a harsh I environment. Coordination of this effort was assigned to the Generation Electrical Engineering Branch of the NUSCO Generation Engineering
- Department. The NU - Nuclear Engineering and Operations Policies and l
Departmental Procedures developed using the NU-QAP for guidance applied j to this project. This multi-discipline project basically consists of four parts: I
- 1. Definition of environmental service conditions, i, 2. Definition of Category 1 Equipment.
() 3. Retrieval and review of qualification documentation.
- 4. Program of surveillance and maintenance.
i The overall project administration is directed by Nuclear Engineering-and Operations (NEO) Procedure NEO 2.01, Preparation, Issuance and Control of Project Assignments. All work done und'r this project assignment was and is subject to the quality assurance procedures out-lined in the NU-QAP Topical Report. i Part 1 of this project was to define the environmental service conditions at Millstone Unit 2 for the spectrum of accidents outlined in IE Bulletin j 79-01B. QA Category 1 calculations were performed by each support j discipline in accordance with the appropriate departmental procedures. The use of outside contract help in this area was accomplished using QA Category 1 Purchase Requisitions in accordance with Procedure NEO 2.03, Preparation of NUSCO Purchase Requisitions and Review of NUSCO Purchase Orders. 4 l Part 2 of this project was definition of the Category 1 Electrical Equipment required to be operable during and after the accidents outlined in IE Bulletin 79-01B. Utilizing the DOR guidelines attached to 79-OlB, NUSCO Generation Electrical Engineering with the support of Generation Mechanical Engineering and the Nuclear Operations Group designated the systems and equipment required for each accident scenario. Blending these data with that of Part I resulted in a list of equipment required (}
. - - . . . . . , , . . . . - _ _ . . . _ _ . _ _ , _ _ _ _ . , _ . _ . _ . , _ . . _ . , _ _ . _ . _ _ . . . _ _ _ . . , _ , _ _ ~ . _ _ _ _ - _
_m _ . - . ._ -
to function in a harsh environment. This listing, developed by NUSCO f-( personnel governed by their departmental procedures, was reviewed by each support discipline, including Operations prior to inclusion in the 79-OlB response. Part 3 of the project required acquisition and review of the Qualification Documentation for that equipment listed in Part 2. Qualification informa-tion was obtained from r.he Nuclear Records Facility, described in NU-QAP Topical Report or from the equipment vendor. Where vendors required a fee to search their files for records aforementioned, procedure NEO 2.03 applied. Information to support qualification is maintained in a central auditable file under the direct control of Generation Electrical Engineering. This information contained in the qualification documentation is noted on the system component evaluation work sheet (SCEWS) for the applicable equipment. Generation Electrical Engineering designated an Ad Hoc Group to deal with this issue. The structure designated two (2) Electrical, Instrumentation and Controls Discipline Engineers for Millstone Unit 2, a environmental qualificatfan specialist, and an overall coordinator to verify adequacy of all information in the central file and consequently the SCEW sheet. Part 4 of the project is an ongoing surveillance and preventive maintenance program which is described in detail in Section B.6 of this submittal. The QA Procedures which are being developed for this program will be based, as in the case with all NUSCO NEO Procedures,on the NU-QAP Topical Report. ' Northeast Utilities considers Quality Assurance paramount in safe operation of its nuclear facilities. Environmental qualification of electrical equipment is an issue which has been and will be considered QA Category 1. O V
C. COMPLIANCE WITH THE JUNE :'O, 1982 DEADLINE The information presented in Reference (32) is duplicated below:
"In the Commission's Memorandum and Order dated May 23, 1980, it was stated that:
"By no later than June 30, 1982, all safety-related electrical equipment in all operating plants shall be qualified to the DOR Guidelines of NUREG-0588."
There are electrical components identified in Appendix II for which total conformance to all applicable qualification requirements cannot be demonstrated at this time. In certain instances, a replacement strategy has been identified. It is noted that Northeast Nuclear Energy Company (NNECO) reserves the right to demonstrate conformance to the applicable qualification requirements by constructing enclosures, re-locating equipment, determining that the components are not required for sccident mitigation, determining the component has acceptable failure modes, or demonstrating that the adverse impact associated with component faiiare is acceptable. Adoption of one of the above alternatives rather than replace-ment continues to assure conformance with the June 30, 1982 deadline." Since the docketing of Reference (32), as explained in previous () sections of this report and in the transmittal letter, significant progress has been made toward the establishment of a more realistic deadline. NNECO has therefore prepared this report assuming that the Commission will accept the Staff recommendation to extend the deadline generically until June 30, 1983. NNECO has initiated plans for achieving full compliance with this extended deadline, as des-cribed for each component in Appendix II. Should the Commission not implement the Staff recommendation, or should NNECO find that additional time beyond June 30, 1983 be required for specific components, supplements to this report will be provided as appropriate.
. . . . - . - _ _ . ~ . - - . . . -. . _ _ _ - - _ . . . - - . - - - . - . - - - ,.
1 D. RESPONSE TO APPENDIX D OF THE SER () Appendix D to Reference (44) constituted the Staff's interpretation of a safety-related systems list, and included a safety-related i display instrumentation list. NNECO han previously provided the basis for this list for Millstone Unit No. 2 by providing Appendix I to Reference (32) , the Master Listing of Electrical Components by System. 1 1 q During the July 7 - 10 meeting, the Staff verbally requested that the list of safety-related display inst,uments be segregated into i two groups. The first group would be thO minimum of instruments required to achieve safe shutdown; these therefore require en-vironmental qualification. This listing :.s provided on the attached sheet, which also indicates the SCEW sheet number j associated with.that instrument. The second listing addresses
- those safety-related instruments which are exempt from quali-fication for the reasons provided.
I i I 1 O
Dockst No. 50-336 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL FOUIPMENT Om MILLSTONE UNIT 2 SAFETY-RELATED DISPLAY INSTRUMENTATION LIST 1 - Requires Environmental Qualification Parameter SCEWS
- 1. Pressurizer Pressure 27-A, 32-A
- 2. Pressurizer Level 30-A
- 3. Pressurizer Relief Valve Monitors 17-C, 18 , 19-C,-20-C
- 4. RCP Loop Temperature 5-C
' s
- 5. Steam Generator Pressure 31-A
- 6. Steam Generator Level 28-A, 29-A, 9-C
- 7. Auxiliary Feedwater Flow 8-C
- 8. Containment Pressure 121-B
- 9. Containment Sump Level 16-C j
- 10. Containment High Renge Radiation Detectors 15-C 1
I + I i O 8/21/81
i Docket No. 50-336
- ENVIROW ENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT i MILLSTONE UNIT 2 SAFETY-RELATED DISPLAY INSTRUMENTATION i LIST 2 - Exempt from Environmental Qualification Parameter Exemption Justification ,
i
; SI Tank Pressure The SI Tank System is passive in r.ature SI Tank Level and completes its function early > to the SI Tank Recirc Flow DBE (LOCA). Instrumentatien is utilized during normal operations and wnnid not be relied upon during the accident.
i Volume Control Tank Pressare The VCT and Let Down Gystems are isolated Volume Control Tank Temperature from the Reactor Coolant System in the Volume Control Tank Level event of an accident (by SIAS and CIAS).
; Let Down Ht Exchanger Temperature This instrumentation is utilized during j normal operation and would not be relied j
upon during the accident, i Charging Pressure The Charging pumps are positive displace-
. -() Charging Flow Charging Temperature ment pumps. When pumps are in operation, header pressure will be equal to RCS
) pressure which is determined utilizing , i ] qualified instrumentation. Flow is determined j by number of running charging pumps during 1 the accident. Charging temperature is ! utilized during normal operations as are.
- pressure and flow, and would not be relied upon during the accident.
] ) ! Pressurizer Temperature The pressurizer temperature instrumentation is utilized during normal operations and would not be relied upon during the accident. Pressure Relief Valve "emperature The pressurizer relief valve temperature sensors would not be relied upon during the accident. The qualified acoustic-valve monitoring system will provide indications on an open relief valve with more assurance than the temperature elements. 1 I i
- - - . - . _ - . _ . , ,,_.-.,,,_m ,m-...-. , , , , . . , . . _ . . . - ~ . . . _ . , _ . - _ . , . _ , _ . , . . . - ~ , - . . - , - - , , - - . . . . . , . - . _ . - -
LIST 2 - Excipt from Environocntal Qual. Docket No. 50-336 Page 2 Parameter Exemption Justification Quench Tank Pressure The Quench Tank instrumentation is Quench Tank Temperature utilized during normal operations and would Quench Tank Level not be relied upon during the accident. This instrumentation would be of limited use in the event of an accident as the rupture disk is rated to release at 100 poundo. Leakage past the relief valves would be detected by the acoustic valve monitoring system during a small break scenario, and the Quench Tank is not used in large break scenarios. RBCCW Flow Proper valve alignmens and pump operation verify adequate flow in the RBCCW System. Excessive flow would be noted by the pump motor current indication which is not located in a harsh environment. RCS Differential Pressure RCS fferential Pressure indication is only ved during normal plant operation. During the postulated accident the reactor coolant pumps are secured and RCS differential pressure indication would serve no function. Containment Temperature Containment Temperature and Humidity Containment Humidity indication is used during normal operation and is not required during the postulated accident. Shutdown Cooling Temperature Verification of Shut Down Cooling System operation would be accomplished by trending qualified RC:1 temperature indication. HPSI Pressure HPSI, LPSI and containment spray pressure 1 Pressure and flow indication can be verified by C., inment Spray Pressure proper valve alignment and nump operation. Excessive or insufficient motor current. HPSI Flow can be interpreted by the operator to LPSI Flow determine the condition of the system. Containment Spray Flow O 8/21/81
?SPENDICES (m
t I. MASTER LISTING OF ELECTRICAL COMPONENTS BY SYSTEM See Reference (32). II. SYSTEM COMPONENT EVALUATION WORK SHEETS (SCEWS) AND JUSTIFICATIONS FOR CONTINUED OPERATION The SCEWS are the individual component comparisons between available documentation and qualification requirements. The format of I&E Bulletin No. 79-01B has been utilized for this effort. For instances where the qualification documentation is insufficient, justification for continued operation is provided on an adjacent page(s) in t?.e Append:x. Only those components which are required to mitigate the ef fects of a IDCA or HELB which results in the harsh environment for that componsnt are addressed. The profiles to which the equipment must be qualified are included in Appendix II. III. RESPONSE 'IO AUDIT REPORT DATED OC'IDBER 14, 1980 See Reference (32). ew
DOCKl"P NO. 50-3 % i ! l NORTIfEAST NUCLEAR ENERGY COMPANY MILLSTONE UNIT NO. 2 APPENDIX II SYSTEM COMPONENT INALUATION WORK 3:!EETS (SCEWS) AND JJSTIFICATIONS FOR CONTINUED OPERATION 9 l AliGUST , 1981 e
-- , - - - - . . - - - - - - - - - . , - - . . . . _ _ _ _ - - _ - - - - . - - . . , ~ . . . . . . . - . _ _ . - - . - , , _ , - _ - - . . , . . . - . _ , .
(Aj Docket No. 50-336 EINIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT MILLSTONE UNIT 2 GENERIC REPIACEMENT SCHEDULES No. 1 The replacement of this group of equipment is scheduled to commence with the next refueling outace which is currently scheduled to commence in December 1981. In the event that the replacement schedule is subsequently modified, the Staff will be notif ied of the revised schedule in subsequent correspondence. No. 2 The present delivery schedule for the replacement equipment in this gro.ap is not compatible with the next planned refueling outage currently scheduled to commence in December 1981. The replacement will occur no later than the first refueling outage following the receipt of fully qualified components. {v} This will be accomplished by June 1983, assuming procurement and installation delays do not preclude replacement by that date. In the event of the latter, justification for an extended implementation schedule will be provided in sub-sequent correspondence. m U
REV. 8-21-81 INDEX . _. SCEW SHT. NO. 53 TEM-125 VDC 120 VAC 4160V 480V Load Centers Reactor Cooling 11-A, 20-A Valve HV1060,1062,1064 95-B, 113-B Valve HV7311 1-C l Valve RC403, 405 Pz Heaters, Prop. 34-A, 35-A Valve RC414-417, 422-425 Safety Injection & Cntmt. Spray 25-B HPSI Pumps MP41 A, B, C 26-B LPSI Pumps MP42A & B 21-B C.S. Pumps MP43A & B 13-B Valve 51654, 653 is-B O vaive S1662 Valve 51651 28 A 10-A, 23-A ' ' Valve SI614 8-B Valve S1616, 626, 636, 646 9-B Valve 51617, 627, 637, 647 7-B Valve S1615, 625, 635, 645 83-B Valve HV3008, 3009 Valve HV3010, 3011 89-B Valve HV3021, 3022 16-8 Valve 51411, 412 24-A l Valve S1652 13-B Valve SI656 15-B Valve SI663 13-B . Valve 51655 10-A, 23-A Valve S1624, 634, 644 108-B, 116-B Valve HV7312 94-B Valve 51659, 660 10-A, 25-A Valve SI618, 628, 638, 648 47-B, 47-Ba Valve SI657 43-B, 10-D l Valve 51306 (Fr 306) Chem. & Volume Cnti. Boric Acid Pumps MP19A & B 84-B Valve CH501, 508, 509, 514 Boric Acid Tank HTR's P141, 142, 143, 144 A Valve CH512 O_. Valve CHS10, 511
REV. '8-21-81 Valve CH505, 198, 506 ll-A, 19-A, 102-B, 120-B
- (i 10-A, 16-A V Valve CH515, 516
- Valve CH517 10-A, 15-A
- Valve CH518, 519 10-A, 14-A Valve HV2524, 2525 10-B, 51-B, 52-B Charging Pumps MP18A, B C 85-8 Flush Pumps MP97A, B, C Valve CH192 Volume Cnt1. Tank Controls
, Valve CH504 25-D i Feedwater Aux. Feedwater Pumps MP9A, B Valve HV5275, 5276 14-B Valve HV5279 Valve HV5419, 5420, 5421, 5422 46-B, 46-Ba SGFPT - H5A & B Main Fdwtr Cnti Valve FV5268, 5269 Service Water Service Water Pumps MPSA. B, C Valve HV6399 Valve HV6482 Valve HV6489 Valve HV6100 Valve HV6438, 6439 72-B () Valve HV6389, 6397 Service Water Strainer ML1A, B, C Valve TV6303, 6307A, 6306, 6307B 70-B, 71-B RBCCW RBCCW Pumps MP11A, B, C 29-B Valve HV6731, 6735, 6050, 6055, 6315, 6316 53-B, 54-B, 55-B, 56-B Valve HV6002, 6003 Valve HV6013, 6014, 6011 Valve HV6096, 6095 ll-B Valve HV6108, 6106 12-B Valve HV6072, 6073, 6075, 6077 96-B , 107-B Valve HV6080, 6084, 6088, 6092 97-B, 98-B,106-B ,112-B Valve HV6739 Valve HV6004, 6006, 6005, 6007 Valve HV6015, 6017, 6016, 6018, 6012 Inst. & Sta. Air Valve HV7083 99-B
, M. 8-21-81 Main Steam .
Valve HV4218, 4222 17-B, 19-B Valve HV4189, 4191 18-B, 20-8 Valve HV4250, 4251 57-B, 58-B Valve HY4246, 4L48 49-B, 50-B Valve HV4217, 4221 40-B, 40-Ba Valve HV4223, 4224 & PT-4223, 4224 36-B 36-Ba Valve HV4193, 4209 66-B, 66-Ba Aux. Bldg. Ventilation Fuel Handling Fan MF20 Fuel Handling Damper HV8141, 8275, 8326 E.S.F.G.D. Damper HV8247, 8133, 8249, D.C. Sw. Gr. Fan MF54A & B Batt. Rm. Exhaust Fan MFil2A & B Ctmt. & Encl. Bldg. Vent Cntmt. Air Fan MF14A, B C, D 8-A Cntmt. Purge Fan MF23 Cntmt. Sample Fan MF39A & B E.S.F.G.D. Air Unit MF15A & B 23-B Encl. Bldg. Fan MF25A & B Post Incident Fan MF18A & B 9-A Cntmt. Rad. Mon. Valve HV8121, 8122 O d Cntmt. Purge Valve Purge Fan Iso-Damper HV8082 HV5050 10-A Cntmt. Purge Damper HV8150, 8151 10 4,17-A Encl. Bldg. Damper HV8079 Encl. Bldg. Damper HV8074 Cntmt. Valve HV8128 Encl. Bldg. Damper HV8153 E.S.F.G.D. Damper HV8306 Fuel Handling Damper HV8062 E.B. Filt. Damper HV8254 E.G. Filt. Htr. X61A, B Cntmt. Rad. Mon. Valve HV8124 Cntmt. Purge Valve HV8125, 8080 10-A Encl. Bldg. Damper HV8081 Cntmt. Purge Damper HV8126 Encl. Bldg. Damper HV8127, 8073, 8070 Encl. Bldg. Valve HV8078 Fuel Handling Damper HV8143 Encl. Bldg. Damper HV8063 E S.F.G.D. Damper HV8312 H Purge Valve HV8377, 8378, 8379, 8380 11-A, 21- A H Recombiner H29A & B 7-A S eam Jet Damper HV8654, 8695 Cntmt. Leak Damper HV8650, 8651 Cntet. Rad. Mon. Valve HV8656 O V
REV. 8-21-81 () Aux. HVAC Cnt1. Room Fan MF21A & B Cntl. Room Fan MF31A & B Cntl. Room Fan MF32A & B D.G. Room Fan MF38A & B Cntl. Room Damper Cntl. Vital Sw. Gr. Rm. Fan MF51 & 52 Chilled Water Pump MP122A & B Chilled Water Pump Valves HV8846, 888;, 8848, 8850 Chilled Water Pump Valves HVR853 P's54, 8855. 8856 Cnt1. Rm. Htrs. X60A & B Cntl. Rm. Compressor MF22A & B Cnti. Rm. Condenser MF36A & B Cntl. Rm. HVAC Ckts. Misc. Chiller X169A & B Sw. Gr. Room Valve PV6925, 6926, 6927 Sw. Gr. Room Fan MF133 & 134 Clean Liquid Radwaste Prim. Drain Tank Valve HV9015, 9016, 9230 11-A, 19-A, 100-B, 119-B Gas & Aerated Liquid Radwaste Waste Tank Valve HV9125, 9126 ll-A, 19-A, 68-B, 69-B, 103-B O Sampling System Valve HV7690 68-Ba, 69-Ba Encl. & Aux. Bldg. Drains Cntmt. Sump Valve HV9150, 9151 11 -A, 19-A , 110-B Rx Trip Sw. Gear Diesel Generator D.G. Power & Cntl. D.G. Unit Cntl. D.G. Air Compressors Boric Acid Heat Tracing Radiation Monitoring Hi Range Rad Detector RE8240, 8241 122-B, 15-C l O i . . - . - . - - - - - - -_-_ . - _ - _ _ _ _ _ . _
. REV, 8-21 81
-5 Instrumentation
({]) 27-A, 30-A Pz. Pressure & Level P100 & L110 P102 32-A
~
Pz. Pressure 2-C, 1-D Pz. Pressure P103 & P103-1 L103 2-D Pz. Level 3-D Pz. Temp. T101 & T109 Pz. Relief Valve Monitors ZS200, 201, 402, 404 17-C 18-C,19-C, 20-C Pz. Relief Valve Temp. T106,107,108 Quench Tank Pressure P116 Quench Tank Temp. T116 Quench Tank Level L116 RCP Loop Pressure Diff. Pill & 121 T112 & 122 5-C RCP Loop Temp. RCP Loop Temp. T111,115,121 & 125 4-D, 5-D RCP Loop Temp. T103,104 & 105 P1013 & 1023 31-A S.G. Pressure 29-A, 9-C S.G. Level L1113 & 1123 5.G. Level L5271, 5272, 5273, 5274 28-A Note: See pages 192 & 193 for S.G. Atmosphere Press. P-4223 & 4224. F5277 & 5278 8-C Aux. Fd. Flow 15-D Cond. Storage TK Level L5282 HPSI Pressure P301 P302 9-D LPSI Pressure Cntmt. Spray Pressure P303 F311, 312, 321, 322 11-D HPSI & LPSI Flow Os
- HPSI & LPSI Flow F331, 332, 341, 342 11-D Cntmt. Spray Flow F3023 & 3024 S.I. Tank Pressure P-311, 321, 331, 341 S.I. Tank Level L-311, 321, 331, 341 S.I. Tank Flow F305 Vol. Cnt1, Tank Pressure P225 7-D Vol. Cnt1. Tank (LetdownTemp.) T224 & 225 L226 8-D Vol. Cnt1. Tank Level B. A. Tank Level L206 & 208 B.A. Pump Pressure P206 & 208 6-D Charging Pressure & Flow P212 & F212 Charging Temp. T229 & 221 Shutdown Cooling Temp. T351 12-D RWST Level L-3000 F6034 & 6035 19-D, 20-D RBCCW Flow 91-B Cntmt. Pressure P8113, 8114, 8115, 8116 Cntmt. Pressure P8117 Cntmt. Temp. T9096 Cntmt. Humidity H8064 E.B.F.S. Pressure P8071 & 8075 E.B.F.S. Pressure P8060 E.B.F.S. Temp. T8072 & 8076 Charging Pump Cont. PS224X, 224Y, 224Z 86-B Containment Press. PT8238, 8239 121-8 Cont. Sump Level LT8242, 8243 16-C p)s x- RBCCh ? amp Pressure PS6119A, B, C 67-8
.
- REV. 8-21-81 Reactor Protection .
~
Turbine Trip PS4597A, B, C & D 14-C Nuclear Power S. G. Pressure (see page 444) Pz Pressure (see page 420) Pz Thermal Margin (see page 436) R.C. Lo Flow (see page 433) S.G. Level (seepage 447) Ctmt. Pressure (see page 477) Mag Jack MG Ld Shed Control Elem. Assembly CEDA Fans MF13A, B, C CRD PWR CEA 1 thru 69 C.R. Reed Switch CEA 1 thru 69 Electrical Penetrationc CONAX 2-A, 36-A Terminai Blocks 3-A, 1-B Cable Low Voltage Power 4-A, 4-B O-coatroi Instrument (Cerro) s-^ 3-8 6-A, 5-B Instrument (Kerite) 6-Aa, 5-Ba Instrument (Coaxial) 37-A , 122-B 5000 V Power 2-B Motor Control Centers MCC B52 30-B MCC B51 B61 31-B Misc. Electrical Equipment Terminal Blocks (Elect. Penetration) 3-A, 1-B PAM (Weidmuller) 38-A Electric Conductor Seal Assemblies (CONAX) 12-A SetScrewConnectors(Ideal) 13-A Instrumentation (Cold Shutdown Only) Aux. Fd. PP Speed S4194A 13-D Aux. Fd. PP Press. PS281,5284,5289 14-D, 16-D, 17-D PW Flow F210X,Y PMW Level L7277 RECCW Sd Htx Flow F6042,6043 21-D , 2 2- D RBCCW Sg Tank Level L6001,6730 18-D, 24-D RBCCW Hx Temp Ctl, TIC 6306, 7 & 8 23-D t
REV. B-21-81 CONTEN'rS O SYSTEM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPONENTS INSIDE THE CONTAINMENT 2A - 38A SYSTEM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPONENTS OUTSIDE THE CONTAINMENT IB - 122B SYSTEM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPONENTS REQUIRED ONLY BY PLANT EMERGENCY IC - 20C OPERATING PROCEDURES MISCELLANEOUS ELECTRICAL EQUIPMENT DOCUrEirr REFERENCE LIST SUPPLEMENT ENVIRONMENTAL TDfPERATURE PRESSURE PROFILES PROFILE NUMBERS INCLUDING 2-42 TEST DATA TABLES TABLE NUMBERS INCLUDING 2A - 6B SYSTDi COMPONENT EVALUATION WORK SHEETS- SHEETS INCLUDING
.0MPONENTS REQUIRED ONLY FOR TRANSITION 1D-25D FROM HOT STANDBY TO COLD SHUTDOWN O
O O O Faci 2 *: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONt'NT EVALUATION WORK SIIEET Docket: 50-336 EtNIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS MET!!OD Parameter Spec. Qual. Spec. Qual. System: Containment operating Continuous Continuous 1- 2.e) Sequen*ial Plant ID No. : EB2,WB2,EB4, Time Test EC1,EC3,WC3,WC5 Cmponente Low Voltage Temperature Pro f ile 18 Profile 36 2.d) ( F) D Simultan-Power 6 Control Electri-cal Penetrations e us Test Manufacture: Pressure Pro 1ile 19 D CONAX (PSIA) Profile 37 2.d) Simultan-cous Test Model Number: Relative Simultan-7852-10000 Ilumidity (%) 100 100 1. 2.d) eous Test Function: Maintain elec-trical continuity through Chemical the cont. struct. Spray 2400 PPM 3000 PPM F 2.c) Simultan-Accuracy: Boron Boron eous Test Not Required Service:Varicus 1.ow Radiation Sequentla1 8 Voltage Power 6 Control 9.4 x 106 R 2.2 x 10 M 2.a) Test Chts. Incation: Containment Aging Flant Design Sequential EL 14*6" 40 Years A40 Years Life 2.b) Test Flood Ievel Elev: (-)l4'4* NA NA NA NA NA Above Flood Level: Yes X Subnergence Mn
*Documentaticn
References:
Notes:
- 1. Bechtel Technical Spec 7604-E-34 NUSCO Specification SP-GEE-45
- 2. CONAX Qualification Test Report IPS-556.2 a) Page 14 b) Par 5.6.2,Page 15 c) Par 5.12.1.2,Page 31 d) Par 5.12,Page 31 e) Par 5.7,Page 18 11-1-80
4 SCEWS No. 7-A TER No. I Date: 8/21/81 EQUIPMENT ENVIRONMDITA1, QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns.(A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. () III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable i i O
O Faci:
- Millstone Nuclear Pr. Sta.
O o Unit: Two SYSTEM COMPONENT EVALUATION WORK SIfEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Passive Device See System: Various Operating Continuous Continuous 1. slant ID No.: Time Qualitied Qual'. By Design Box Conqx>nent : Electrical TemperatureProfi1e 18 Simultaneour D 4 Test Penetration Term, Blocks ( F) Note 2 51muR aneou Manufacture: General Pressure Pro fi l e 19 Test Electric Co. (PSIA) Relative Simultaneout Model Number: CR-151 Function: To terminate connections to electrica] ' Chemical 2400 PPM Note 1 F I penetrations Spray Note 1. Boron Note 1 Accuracy: Not Required Radiation *Y
- Y l Service: V trious circuits 9.4 x 10 6 R 7
1.2X10 R !! 4 literature search riant Incation: Containment Aging Design Arrh enius EL 14'-6" 40 yrs
- 12x106 Life 5 Analysis yrs Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Submergence NA NA NA NA NA nn
- Documentation
References:
Notes: 1. Term. blocks are mounted in sealed boxes. No direct impingement . Protection considered adcguate to
- 1. Bechtel Tech. Spec. 7604-E-34 2.
Prevent failure due to an accident. 3.
- 2. Loc a Qualification profiles from Doc. Ref. 4.
o c. 260
- 4. GE Ltr. G-EH-8-16 dated 2/2/78 Temp 260 320 340 320 Term Block Locatest Forwarded Press PSIG 21 75 103 75 21 by G.E. Ltr. R.F. Thibault to R. Derosa dated 12/14/79 RH % 100 100 100 100 100 G.E. Ltr. G-EH-9-1-141 dated 10/18/79 Duration 1.5 Days 1.5 Hrs. 3 Ifrs. 4.5 Hrs. 8 Days
- 5. Wyle Report 17436-48 dated 2/3/81 3-A 8-21-81
SCEWS No. 3-A TER No. 7 Date: 8/21/81 f) EQ'J1PMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Summary of new inf ormation on SCEW sheet.
Aging analysis utilizing Arrhenius Methodology completes qualification. II) Response to SER concerns. (A) I Aging is addressed above and in the body of the Submittal. III) Response to TER concerns, r~x ( ,). Same as II. IV) Proposed corrective action and schedule. Refer to description of plant surveillance and preventive maintenance program in body of submittal. V) Justification for continued operation. Not applicable. (']\
\._
Faci' O . Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONE.NT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Simulta-System: Electrica1 Operating neous Plant ID No.: Time Continuous Continuous 1. e) Test Component: Low Voltage Temperature Profile 18 P'wer Cable ( F) Profile 2 D 4.c) Simultaneous Test Manufacture: Anaconda Pressure Proti1e 19 (PSIA) Profile 2 D 4.c) Simultaneous Test Model Number: EPR Insul, Relative CSPE Jacket Humidity (%) 100 100 1 4.a) Simultaneous Function: Wirewyas for Test Low Voltage Motors, ' Chemical D.C. Systems, Heater, etc. Spray 2400 PPM 3000 PPM e 4.a) Simultaneous e Accuracy: Not Required Boron Boron Test Note 1 Service: 480 V, 120 V AC, Radiation 8 1.5 x 10 8.1 2X10 B 2 4.b) Sequential 125 VDC Circuits Test g Location: Containment Aging Plant " Simulated Design Sequential 40 Years 40 Years Life 4.f) Test Flood Level Elev:(-)14'4" Above Flood Level: Yes X Subnergence NA NA NA NA NA nn
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-E-17 1. Chemical spray consists of:
- 2. Nr vo Memo. D.W. Miller to R.J. DeRosa, 3000 PPM Boron as Boric Acid
?;EE-79-E-281 Dated 5/21/79 0.064 Molar Sodium Thiosulfate 4 FIRL Test Report F-C-4350-3 Adjusted with Sodium Hydroxide to a PH of 10.5 at Room Temp a) Page 3-2, Sec. 3.3 d) Page 3-1 b) Appendix C e) Page 3-3 c) Fig. 2 f) Attachmeat dated May,1977 4-A 11-1-80
SCEWS N3. 4-A TER No. 3 l Date: 8/21/81 r EQUIPMENT ?;WIRONMENTJ1 QU/11FICATION SER/TTR REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on CCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive nu'ntenance program contained in body of submittal. III) Response to TER concerns. O Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. l IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. 1 V) Justification for continued operation. Not applicable 4
O O O i Faci. *: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WOIE SiiEET Docket: 50-336 7 EINIRONMENT DOCUMEtr"ATION REF* QUAL. OUTSTANDING l EQUIPMENT DESCRIPTION METI!OD ITEMS Parameter Spec. Qual. Spec. Qual. Simulta-System: Electrical Operating Plant ID No.: Time Continu us Continuous 1. 4.(d) neous Test Component: Control Cable Te erature Profile 18 D 4.(a) Simultan-Profile 3 eous Test-Manufacture: Kerite Pressure Profile 19 (PSIA) Profile 3 D 4.(a) Simultan-cous Test Model ': unber: FR Insul Relative 100 100 1. 4.(a) Simultan-FR Jacket Humidity (%) eous Test Function: Wireways for control & Low Lcvel Pwr ' Chemical 3000 PPM i Ckts Spray 2400 PPM Boron F 4.(b) Simultan-N t Required x . . c) Var ous Control and Low Level Pwr Ckts. Incation: Aging Containment 5. Sequential Simulated 40 Years i 40 Yrs 1. Test Flood Level Elev:(-)l4 '4" Above Flood Level: Yes X Subnergence NA No N NA NA NA NA i'
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-E-18 1. Chemical Spray Consist of:
- 2. aOSCO Memo. D.W. Miller to R.J. DeRosa 0.28 Molar 113 B0 3 (3000 PPM Boron)
NEE-79-E-281 Dated 5/21/79 FRIL Test Report F-C4020-1 0.064 Molar NA223 S0 4. (a) Fig. 1 N20ll to make a PH of 10.5 at 77 F (b) Page 3-1 _ (c) Page 5-2 (d) Page 6-1 11-1-80
- 5. Kerite Engineering Memorandum 178A, May 1, 1979 5-A
SCEWS N3. 5-A 4 TER Ns. Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2
< Docket No. 50-336 I) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance pragram contained in body of submittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. 1 ( Equipment will be incorporated into plant surveillance and preventive l maintenance program. V) Justification for continued operation. Not applicable i l l l u I v-- ..---- .., n - , , , . - , - - . - ,-.,n. . , ., , , , , - , _ , . . . - . . , . , , , , , , - - , , , , , , , , . n_ , ----..,,..,, ,.n. . - - . _ , - . _ , - . , , . , ,-e,
O Q 1 %)
; Faci y: Millstone Naclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* OUTSTANDING
)
4 EQUIPMENT DESCRIPTION QUAL. MET 110D ITEMS Parameter Spec. Qual. Spec. Qual. 4 System: Instrumentation Operating Continuous Continuous 1. 4.d) Note 1 Plant ID No.: Time Component: Instrument Temperature Profile 18 Cable PF) Profile 4 D 4.c) Sinultaneous Test
- Manufacture. Pressure Pro f i1e 19 The Rockbestos Co. (CERRO) .
(PSIA) Profilc 4 D 4.c) Simultaneous Test
- j Model Number: Relative j XLPE Insul-Neoprene Jacket flumidity (t) 100 100 1. 4.b) Simultaneous Function: Test
- i I Wireways for Instrumenta- Chemical tion Ckts. Spray 2400 PPM 3000 PPM F 4.c) Simultaneous
- Accuracy
- Boron Boron Test
- i Not Required l Service: Radiation General Instrumentation 1.5 x 10 8 R 2X10 R K. 4.a) Sequential Test
- Location: Containm'.7t Aging Simulated Sequential 1
40 Years 40 Years 1. 4.e) Test
- Flood I4 vel Elev:(-)l4 '4"
- Above Flood Level
- Yes X Subnergence NA NA NA NA NA Mn
- Documentation Peferences: Notes:
, 1. Bechtel Technical Spac. 7604-E-19A
- 2.
- Insulation only
! 3. 1. Cable involves low current only. Continuous
- 4. CERRO Cert. Report dated 2/1/77 operation is inherent.
(a) Page 3, par. V (b) Page 4, par. V (c) LOCA Profile page 8 ! (d) Page 1 (e) Page 2 6-A 11-1-80
SCEWS No. 6-A TER No. 5 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new inf ormation on SCEW sheet. J None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. O Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging antlysis. IV) Propeseo corrective action and schedule. i
. Equipment will be incorporated into plant surveillance and preventive maintenance program.
l V) Justification for continued operation. Not applicable l l t O
O f"*'s) ( Fccil V : listona Nuclear Pr. Stn. SYSTEM COMPONErr"E. 0ATION WORK SHEET
'b Unit: TE Docket: 50-336 ENVIRONMENT DOCUMENTATION REP
- QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Socc. Qual.
System Instrumentation Operating Centinuous Continuous 1. 3.d Simultaneou s Plant ID No.: Time Test Component: Instrument Cab' aTemperature Profile Profile D 3.a) Simultaneou:; ( F) 18 3 Test Manufacture: Kerfte Pressure (PSIA) Profile Profile D 3.a Simultaneou , Model Number: 600V 19 3 Test Relative 100 100 1. 3.a) Simultaneoua Humidity (%) Test
- Function: Wireways for Instrumentatiof Genical 2400 ppm 3000 ppm Circuits Spray Boron F 3.b) Simultaneou::
Accuracy: Note 1 Test Not Required Service: Radiation 1.5 X Ib0 R 2 X 108 R 2. 3.c) Simultaneou:: General Instrumentation Test tocatJon: Agin9 40 yrs. Simulated Sequential containment 40 yrs. 1. 4. Test Flood Imvel Elev:~14'4" N/A N/A N/A N/A N/A Above Flood Imvr*. YesX Suhmergence m
- Documentation
References:
Notes: 1. Chemical Spray consists of: 0.28 Molar
- 1. NUSCO Standard Specification for Instrument Cable 113 B03 (3000 ppm Boron) 600 volts SF-GEE-14
- 2. NUSCO memo D. W. Mille r to R. J. DeRosa NEE-79-E-281 0.64 Molar NA S 0223 dated 5/21/79 N,0li to make a pli of 10.5 at 77 F
- 3. FIRL Test Report F-C4020-1 dated March, 1975 a) Fig. 1 ,
c) ; age 5-2 b) Page 3-1 d) Page 6-1
- 4. Kerite Engineering Memorandum 178A, May 1979 6- As 11/1/80
6 SCEWS NO. 6-Aa 6 TER No. Date: 8/21/81 4 EQUIPMENT ENVIRONMDITAL QUAI.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50 J36 I) Summary of new information on SCEW sheet. None I II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenonce progran. V) Justification for continued operation. t Not applicable .i I l l l----..-. -. - _ - . . _ _ - . _ _ . _ _ __
O O O Facil : Millstone Nuclear Pr. Sta. SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS EE Sh. 252(H-29A) 253(H-29B) Parameter Spec. Qual. Spec. Qual. System: Post Accident Hyd. Operating Con tinuous-ly one mon 60 pays 1. 4.a) Sequential Plant ID No.: Cont. Time Test H-29A, H-29B or more Component: Temperature Profile 18 Sequential Profile S A D 4.e) Hydrogen Recombiner (OF) (See note 1.) Test Manufacture: Pressure Profile 19 D (PSIA) 4.b) Simultaneous Westinghouse Proffic 5 Test Model Number: Relative Simultaneous Humidity (%) 100 100 1. 4.b) Dwg. No. ME-7070-1 Test , Function: To limit Hydrogen existing in the Chemical 2400 PPM 2500 PPM F 4.b) Simultaneous containment Spray Baron Test Accuracy: Boron Not Required Service: Radiation Sequential 1.5 x 10 R 2X10 R 2. 4.c) Test Location: Aging Plant esign Sequential ell 4'-6" (H-29A) 40 yrs. 40 yrs. Life 4.d) Test EL38'-6" (H-29B) Flood Level Elev:(-)14'4" NA NA NA NA NA Above Flood Level: Yes X Subnergence Nn
- Documentation
References:
Notes: o
- 1. Bechtel Tech. Spec. 7604-M-510, Page 3,4 1. Containment Temp deminishes to 200 F approx.
- 2. NUSCO me:r.o, D.W. Miller to R.J. DeRosa, hour after a Loca: H. Recombiner is started NEE-79-E-281 dated 5/21/79. 12 hours after a Loca
- 3. 2. Spray consisted of 2500 PPM Boron as Boric
- 4. Westinghouse WCAP7709-L and auppL I-7 acid with Sodium Hydroxide added to give a PH (a) Suppl 3, Par. 3,1.2 of 10 (b) Suppl 2, Page 3-24 (Test 2,3)
(c) Suppl 2, Par. 3.6.2 (d) Suppl 6 Par. 6.3.2 (e) Terp. vs time profile forwarded by Westinghouse 7-A ltr. NE U 3546 dated Oct. 1, 1980. 11-1-80
. ~ _ .
SCEWS No. 7-A TER No. 7 Date: 8/21/81 EQUIPMENT ENVIRONMENTA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Besponse to SER concerns. (Deficiency not listed) Refe- to description of surveillance and preventive maintenance program contained in body of submittal. 1 (} III) Response to TER concerns. SCEW 7-A ref erence 4. is provided by Westinghouse as applicable j to the Millstone Unit 2 Hydrogen Recombiner. IV) Proposed corrective action and schedule. r l Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. l Not applicable l l l m
O Faci] *: Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONENT EVALUATION WORK SilEET Docket: 50-336 EQUIPMENT DESCRIPTION EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METIIOD ITEMS EESH. 206-209 Parameter Spec. Qual. Spec. Qual. System: Cont. Air Recirc. Operating Note 2 1 Yr. 1. 4.d) Sequential Time Test Plant ID No. : F-14A, F-14B
~
Temperature Profile 18 b~m rfent: C ntainment Tame 2A, o 4.c) Mmul tan-F) Air Recirculation Fans 2B eous Test Manufacture: Pressure Pro f 11 e 19 Westinghouse (psyn) Table 2A, 2B o 4.c) Simultan-eous Test Model Number: Westinghouse Relative Syle No. 7180007 Humidity (%) 100 100 1. 4.b) Simultan-Function: eous Test Cool Containment Air ' chemical 9.5 PH Spray 2400 PPM Spray F 4.b) Simultan-Accuracy: Boron Note I eous Test Not Required . Service: Containment Radiation 8 1.5 x 108 R 2X10 K 4.a) Sequential Air Recirculation System- Test 460V Incation: Containment ^91"9 40 Yrs. 40 Yrs. Plant 4.c) Sequential El. 2'-0", 36'-0" Design Test Life Flood Level Elev: (-)14 '4" NA NA NA Sulxnergence NA NA Above Flood Level: Yes X nn
*Eccumentation
References:
Notes:
- 1. Bechtel Technical Sepc. 7604-M-501 1. The chemistry environmtit was obtained using
) 2. a water spray solution of 1.43 weight percent
- 3. PH to a value of 9.5 boric acid and adjusting (2500 PPM Boron)
- 4. Westinghouse WCAP 7829 with soduim hydroxide.
l (a) Page 10,14 (c) Page 33,35 2. The units shall be designed to operate for i (b) Page 15, 37 (d) Page 3 20 hrs. at peak incident conditions and 7 days 1 (c) Page 16 at 15 PSIG, 200 F. 8-A 11-1-80
g $r -
" --M j
SCEWS No. 8-A TER No. 8 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 4 I) Sommary of new information on SCEW sheet. None i
- II) Response to SER concerns. (A)
Refer to description of surveillance and preventive maintenance program i contained in body of submittal. I III) Response to TER concerns. SCEWS 8-A reference 4 is provided by Westinghouse as applicable to the Millstone Unit 2 Car Fans. 1 IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. l t V) Justification for continued operation. Not applicable l 1 l l i O 1 i i ex - - . . , , - , . ,,...,,-.,m ,. .- .-y.,..,-,.,,,,--y-.m._. , - - - , , - - - - . - - , . - _ _ . . . . . - ,.,_.- --.... ,-.--ym,,,
~
O Faci' r: Millstone Nuclear Pr. Sta. O O Unit: Two SYSTF:1 COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION EMVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING g METilOD ITEMS I EE SH. 217,218 Qual. i Parameter Spec. Qual. Spec. System: Operating Continuous 1 yr. I-3.b) simultaneoun Plant ID No.: F-18A, F-18B Time test Caponent: Post Incident Temperature Proffle 18 Profile 25 Recirculation Fans ( F) D 3.b) simultaneous test Manufacture: Joy Mfg. Co. Pressure Profile 19 (Reliance Electric Co. (PSIA) Profile 25 D 3.b) simultaneous Motor) test Model Number:24-17-5-3500 Relative simultaneous Special S/NGF15745, 15746 Humidity (%) 200 100 1. 3.d) test Function: Containment Air Mixinn Chemical Spray 2400 PPM Note 1 F 3.c) simultaenous s Accuracy: Not Required Boron test 8 sequential Service: Post Incident Radiation 1.5 x 10 R IXIO R 2-Recirculation - 460V 3.e) test i Incation: Containment Aging se quential El. 14'-6" 40 yrs. 40 yrs. 1. 3.a) i test Flood Level Elev:(-)l4'4" Above Flood Level: YesX Suhnergence NA NA NA NA NA nn 4
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-507 1. chemical spray per IEEE 323, page 19 (3000 PPM Boron).
- 2. NUSCO mmo, D. W. Miller to R. J. DeRosa, NEE-79-E '81 dated 5/21/79
- 3. Joy y;alification Test Report X-604, 4/6/77, revised 3/20/80 a) page 5 c) appendix A, page 8 b) page 12-17 d) page 1.
e) appendix F, page 1 9-A 11-1-80
i SCEWS No. 9-A TER No. 9 Date: 8/21/81-EQUIPMENT ENVIRONMDITAl. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 i I) Summary of nce information on SCEW sheet. None II) Response to SER concerns. (A) i Refer to description of surveillance and preventive maintenance program contained in body of submittal, i III) Response to TER concerns. i O SCEWS 9-A, re'erence 3 was provided by Joy Manufacturing Company as applicable to the Millstone Unit 2 P. 2. R. Fans. l IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. l V) Justification for continued operation. ! Not applicable i l l l i
O O O Facii : Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONEsT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. _ Operatinq b*9"*"EI"I System: Various Plant ID No.: Various Time P Continuoun P S Component: Stem mounted Temperattre Pro f ile 18
! F) Profile 6 D 5.a) Simultaneous limit witches Test Manufacture : NAMCO Pressure Profile 19 (PSIA) Profile 6 D 5.a) Simultaneous Test Model Nu".tber :
EA-180 Relative 100 100 1. 5.b) Simultaneous 11umidity(%) Test Function: Valve control , interlocks and position Chemical 2400 PPM F Simultaneous indication Spray Note 1 5.b) Accuraty: Boron Test Not Required Service: Various air Radiation g 8 5.c) Sequential OM R 4, operat<_d and motor Test operated valves Aging 40 yrs. Test & Gasket Incation: replacement. Inside Containment 40 yrs. except P.D.L. 2 Analysis
. gasket (2 yrs.) req. every Flood Level Elev:(-)14'4" NA NA Above Flood Level: Yes X Submergence NA NA NA nn
- Documentation
References:
Notes:
- 1. FSAR safety analysis (Ammendment 20) 1. The spray consisted of boric acid, water, sodium Wyle Report 17436-3 thoiosulfate and sodium hydroxide-PH-10 (3000 PPM Boron) 2.
- 3. 2. Model EA-180 limit switches replaced originally NUSCO memo, D. Miller to R. DeRosa, NcE-79-E-281 installed limit switches en the following valves:
4 SI-618 Cil-515 EB-88 SI-614 dated 5/21/79 EB-89 SI-624 SI-628 Vendor qual report, pl .in t file MRIR #1-26-79 CH-516
- 5. SI-634 SI-638 (a) Fig. 1, page 11 o f 11 CH-517 :r/-8082 CH-518 HV-8125 SI-644 SI-648 (b) Page 9 of 11 (c) Page 2 of 11 CH-519 11-1-80 (d) Page 1 of 11 10-A
10-A SCEWS No. 10 TER No. 8/21/81 Date: O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 j Docket No. 50-336
- 1) Summary of new information on SCEW sheet.
None
?
II) Response to SER concerns. (Q31, QT, A) l 1 QM , QT, See TER CAT iia Refer to description of surveillance and preventive maintenance prograr contained in body of submittal. i III) Response to TER concirns. Same as 11. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
. _ - _ . _ . - - . _ . , _ . _ - . . - _ _ _ _ _ - - - _ _ . _ _ . _ . ~ - _ . _ . _ _ _ _ _ - _ . . _ _ _ . _ _ _ , _ _ _ _ _ _ . . _ , _ _ - _ _ _ _
O Facil r: Millstone Nuclear Pr. Sta. O o SYSTEM COMPONE,aT EVALUATION WORK SilEET Unit: Two Docket: 50-336 l ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING J EQUIPMENT DESCRIPTION ITEMS METIfOD Parameter Spec. Qual. Spec. Qual. Sequential
- System
- Various Operating Test Plant ID No.: Various Time P Continuous P 5 Component: Stem mounted Temperature Prof 11e 18
- Profile 7 D 5.a) Simultan-limit switches ( F) cous Test 1
l Manufacture: NAMCO Pressure Profile 19 5.a) Simultan-l Profile 7 D (PSIA) eous Test k Model Number: EA-740 Relative 1. 5.b) Simultan-100 100 fumidity (%) eous Test Function: Valve control interlocks and position Chemical Spray 2400 PPM indication Note 1 F 5.c) Simultan-Accuracy: Boron cous Test l
. Not required Service: Various air Radiation j 8 8
- 4. 5.b) Sequential operated and motor 1.5 x 10 R 2.04X10 R Test 4
operated valves 40 yrs. Test & Gasket J Location: Aging except p.p.L. 2 Analysis replacement Containment 40 yrs. gasket [ req'd every 9 . . ~ (2 vrs.) Plood level Elev:(-)14'4" NA ; NA NA NA 1 Above Flood Level: Yes X Submergence NA Nn G
- Documentation
References:
Notes:
- 1. The spray was composed of boric acid, water,
- 1. FSAR safety analysis (Ammendment 20) sodium thiosulfate, and sodium hydroxide,
- 2. Wyle Report 17436-3 PH between 10 & 11 (3000 PPM Boron).
- 3. Model EA-740 limit switches replaced originally
- 4. NUSCO memo, D. Miller to R. DeRosa, NEE-79-E-281 2.
installed limit switches on the following valves: 5-21-79 IIV-9230 llV-9151 liv-1060
- 5. Vendor qual. report, plant file MRIR #1-26-79 IIV-9125 IIV-1064 IIV-8380 a) Fig. 1, Page 11 of 12 IIV-1062 HV-8378 Cil-506 b) Page 7 of 12 c) Page 8 of 12 11-1-80 d) Page 3 of 1 11-A
II-A SCEWS No. TER No. II Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket Nc. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (QM, QT, A) QM, QT, See TER CAT iia Refer to description of surveillance and preventive maintenance program contained in body of submittal.
- III) Response to TER concerns.
Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
.O Facil '
Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPriENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Various Operating Simultaneous Plant ID No.: Time P Continuous P 5.b) Test Component: Electric Temperature Profile 18 Conductor Seal Assembles FF) Profile 8 D 5.b) Simultaneous for SMLS's Test Manufacture: Pressure Pro file 19 CONAX (PSIA) Profile 9 D 5.c) Simultaneous Test Model Number: Part No. Relative 100 100 1. 5.d) Simultaneous N-11001-32, N-11001-33 Humidity (%) Test Function: Provide a sealed cable ' Chemical entrance for SMLS's Spray 2400 PPM Note 2 F 5.d) Simultaneous Accuracy
- noron Test Not required 8 Service: Radiation 1.5X108R 1.5X10 R 4, 5.a) Sequential Valve limit switches Test Location: Aging Containment Sequential 40 Years 40 Years PDL 6 Test Flood Level Elev:(-)l4"4" Above Flood Level: Yes X Submergence NA NA NA NA NA Mn
- Documentation
References:
Notes:
- 1. FSAR safety analysis (Ammendment 20) 1. All modules must be compatible with Fig. 5.3.1
- 2. The test data base configuration was subjected
- 3. to the test profile given in Fig. 5.3.2.
- 4. NUSCO memo D. Miller to R. DeRosa, NEE-79-E-281 2. Chemical spray consisted of boron and NADH with dated 5/21/79 a PH of 10.5 (3000 PPM Boron)
- 5. CONAX qualification report IPS-409 dated 3-9-79 3. Assemblies were purchased under NUSCO P. O. 607 386 a) Par. 5.1 c) Par. 5. 3. 2. 4 for qualified components i b) Par. 5 3.1 & 5.3.2 d) Par 5.3.2.2
- 6. CONAX Qualification Report IPS-325 12-A 11-1-80 l
)
12-A SCEWS No. 12 TER No. Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new inf ormation on SCEW sheet. None II) Response to SER concerns. (QM, QT, A) QM, QT- See TER CAT iia
- Refer to description of surveillance and preventive maintenance program contained in body of submittal, j
i l III) Response to TER concerns. Same as II. l IV) Proposed corrective action and schedule. t Equipment will be incorporated into plant surveillance and preventive naintenance program. V) Justifi:ation for continued operation. Not applicable
.,,,,,,-..-m._.,_._,_,.,, ,__.-,,,,-__.____,,,,~-.m_.,.,,,_,.__-mm-., , , . .,- , , . _ _ . - , , , ,, _ - , _ . . . - .
O O O Facil : Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SliEET Docket: 50-336 ENVIRCNMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METilOD ITEMS Parameter Spec. Qual. Spec. Qual. _ , Passive System: Electrical Operating Design Device See Plant ID No.: Time Require- Qualified Qual. Continuous Continuous ment By Design Box T*mperature Profile 18 Simulta Component: Set screw D 3. neous Connectors ( F) 3 Test Manufacture: Ideal 7: essure Pro f ile 19 Simulta-(PSIA) 3 D neous Test bimulta-Model Number: Cat. Nc. Relative 100 3. Humidity (%) 100 D neous 30-210 and 30-211 Test Punction: Splice Assemblies Chemical 3. SNb-Spray 2400 PPM 2640 PPM F neous Accuracy: N7t required Boron Boron Test Service: Valve limit Padiation 2.4 x 107 R 3 x 108 R 4. 5.a) Analysis i switch circuits Location: Various Loca- Aging Plant tions inside containment 9366 yrs. Dcsign 40 yrs. ,at 12') F Life 5.a) Analysis Flood Level Elev:(-)14'4" NA NA NA Above Flood Level: YesX Suinergence NA NA No
- Documentation
References:
Notes: 1. 2.
- 3. NUSCO memoranda GEE-79-214, CEE-78-358, GEE-79-271 _
- 4. NUSCO memo D. W. Miller to R. DeRosa NEE-79-E-281 dated 5/21/79 WLE Report 17436-1 dated Oct. 8, 1980 5.
a) Page 21 13-A 11-1-80
13-A SCEWS No. I3 TER No. Date: 8/21/81 O EQUIPulNT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. I III) Response to TER concerns. (} Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. I V) Justification for continued operation. I Not applicable i j l i O l 1 I
. . - _ - _ , . , _- , _ . _ . - . _ . . , , _ _ _ . _ . _ - - - - _ . . _ , _ _ . . , , . _ . . . . . . _ . - . . , _ . - - . - - . _ , _ , . . _ . , - . . - - . ~. .
i O Facil *: Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONENT EVALUATION WOPX SHEET Docket: 50-336
- ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.
Simultaneou'i System: Chem.& Vol. Control Operating P Con t inuous P 3.a) rest Plant ID No.: HY-518 Time j HY-519 Component: Selenoid TemperaturePro f il e 18 Profile 10 3.b) Simultaneous Operated Valves (OF) D Test 3.b) Manufacture: Pressure Profile 19 Profile 10 Simultaneous D Test i ASCO (PSIA) J Model Number: Cat. No. Relative 100 100 D 3.c) Simultaneous NP-8320A-185V Humidity (%) Test Function: Pilot Valves for Ch-518 and CH-519 ~ Chemi 1 3.d) Simultaneous Spray 2400 PPM B p Test Accuracy: Not Required Boron Service: Charging Line Radiation 1.5X10 8R 2 x 10 8 R 4. 3.e) Se uential Test Distr. Valves Aging Req. maint. Incation: Containment El. 8'-6" Sequential performed 40 Years 4.4 Years PDL 3 Test every 3 yrs Flood Level Elev:(-)l4'4" AbcVe Flood Level: Yes X Submergence NA NA NA NA NA Hn l
- Documentation
References:
Notes:
- 1. 1. Originally installed valves replaced during
- 2. 8-8-79 outage.
- 3. ASCO Test Report No. AQS 21678/TR Rev. B 2. SMLS Type EA-180 a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Pa r . 9.4. 2.4. 3 4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5-21-79.
e) Appendix D 14-A 11-1-80
I4-^ SCEWS No. 14 TER No. Date: 8/21/81 EQUIPMENT ENVIR0!O! ENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) i i Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. 4 Same as II. l IV) Proposed corrective action and schedule. J l Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O r,-,->,- p.w.-,~w-,,-~,m-_ ,,_e,,e vn ., -mn--,n,-.--m--,nw,, -.,,,,n- .,--n,--,r-,n ,-,.,-.--._,--ew,en.,,w---.~,,-,..w.,wan-- ,er-e-e-w-,-e
4 Facil O : Millstone Nuclear Pr. Sta. o e Unit: 'Ivo SYSTEM COMPONENT EVALUATION WORI'. SilEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS
' METIIOD Parameter Spec. Qual. Spec. Qual.
3.a) Simultaneous Systems Chem. & Vo l . Co n t . Operating P Con t in uou s P Time Test i Plant ID No.: l{Y-517 Component: Sol enoid Temperature Pro fi1 e 18 Profi1e 10 3.b) Simultaneous Operated Valve ( F) Test Manufacture: ASCO Pressure Profile 19 Profile 10 3.b) Simultaneous (PSIA) "" D Model Number: Type Relative 100 100 D 3.c) Simultaneous l Test 200-381-6RF Ilumidity (%) Function: Pilot Valve for Cll-517 ~ Chemical 3.d) Simultaneous Spray 2400 PPM B Test i p Boron Accuracy: Not Required Service: Aux. Spray Radiation 1.5X10"R 2 x 10 8 R 4. 3.e) Sequential Test . Location: Containment Aging Sequential Req. maint. Test performed El. 8'-6" 40 Years 4.4 Years PDL 3 every 3 yrs , i Flood Level Elev:(-)l4"4" Above n'3 m d Level : Yes X Sutsnergence NA NA NA NA NA nn ,
- Documentation
References:
Notes:
- 1. 1. Originally installed valva replaced May, 1979 (Refer to
- 2. W. G. Counsil letter to R. Reid dated 4/18/79)
- 3. ASCO Test Report No. AQS ^*1678/TR Rev. B 2. SMLS Type EA-180 a) Appendix A Pa r . 5 h) Appendix A Fig. 9.2 c) Appendix A Pa r . 8.1. 3 d) Appendix A Par. 9.4.2.4.3 c) Appendix D
- 4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79 11-1-80 15-A
SCEWS No. 15-A 15 TER No. Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL, QUALIFICA* TION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 1 1 I) Sut: mary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and prcventive maintenance program contained in body of submittal. III) Response to TER concerns. O Same as II. r IV) Proposed corrective action and schedule. r Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable J . O t _,_,,v-_,_,,_.,.__.,_,_,,,,_,_.,_,,,,,_,,,._ . , , _ _ _ _ , _ , . . _ , , _ , , , _ _ . . _ - . , _ . . . . , _ , _ - - , , , . _ _ , , _ _ , , . . . . _ , . _ _ _ , , , . , - . .
o L O Millstone Nuclear Pr. Sta. o' Faci) : SYSTEM COMPONENT EVALUATION WORK SilEET Unit: Two Docket: 50-336 . DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION MET!!OD ITEMS Parameter Spec. Qual. Spec. Qual. Approx. 5 Operating sec , rol_ Continuous 5. 3.a) Simultaneous Syster.: Chem. 6 Vol. Cont rol rest Plant ID No.: HV-515 Time lowing a HV-516 Loca. Component: Solenoid Temperature Profile 18 Profile 10 D
~
Test Operated Valves ( F) Pressure Protile l ') Profile 10 3.b ) Simultaneous Manufacture: ASCO (PSIA) D Test I 100 100 D 3.c ) Simultaneous Model Number: Type NP- Relative Test 8320A-185V Ilumidity(%) l Function: Pilot Valves ~' 3.d) Cimulf aneous for CH-515, C11-515 - Chemical Test 2400 PPM g Spray Boron Accuracy: Not Reqeired Service: Letdown system Radiation 1.5X108R 2 x 108 R 4. 3.e) Sequential Test containment isolation Req. maint. Incation: Containment Aging performed Sequential El. 8'-6" PDL 3 Test every 3 yrs. 40 Years 4.4 Years Flood Level Elev:(-)l4'4" NA NA NA Above Flood Level. Yes X Submergence NA NA Nn
- Documentation
References:
Notes:
- 1. 2. 1. Originally installed valves replaced during
- 3. ASCO Test Report No. AQS 21678/TR Rev. B October,1979 outage a) Appendix A Par. 5 b) Appendix A Fig. 9.2 2. SMLS Type EA-180 c) Appendix A Par. 8.1.3 d) Appendix A Pa r. 9.4. .4. 3 e) Appendix D
- 4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79
- 5. Tech. Spec . Table 2.6-2 11-1-80 16-A
.. .- -= -. . - .. _
SCEWS N3 16-A TER No. 16 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALITICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Summary of new information on SCEW sheet.
None t II) Response to SER concerns. (A) Refer to d?scription of sur <illance and preventive maintenance program c7ntained in body of submittal. l I III) Response to TER concerns. Same as II. J IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveilaance and preventive maintenance program. V) Justification for continued operation. j Not applicable I l
I O O O i Facil *: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 1 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METIlOD ITEMS Parameter Spec. Qual. Spec. Qual. _ , i Approx. 5 System: Encl. Bldg. Filt. Sys. Operating Sec. Fol- Con t inuous 5. 3.a)
~
I wing a Sinultaneous Plant ID No.: HV-8150, Time Test IIV-8151 Loca. i i Component: Solenoid Temperature Profile 18 Profile 10 3.b) Simultaneoun Operated Valves ( F) D Test
)
Manufacture: ASCO Pressure Pro f ile 19 Pro t ile 10 J.b) 51multaneou, D Test (PSII.) Model Number: talve Type Relative 100 100 D 3.c) Simultaneoun 206-381-3P"J Humidity (s) Test Function: Pilot Valves for
- EB-88. EB-89 Chemical 3.d) Simultaneous Spray 2400 PPM Tesc Accuracy
- Not Required Boron B F l
I Service: Containment Rad. Radiation 1.5 x 108 R 2 x 108 R 4. 3.e) Sequential d Mon. Isolation Test Location: Containment Aging Req. maint. i El. 38'-6" Sequential performed 40 Years 4.4 Years PDL 3 Test every 3 yrs. Flood Level Elev:(-)l4'4" "^ ^ ^ , Above Flood Level: Yer: X Subnergence Nn
- Documentation Referer.ces: Notes:
- 1. 2. 1. 0.-iginally inetalled valves replaced during Oct. 1979 Outagt
- 3. ASCO Test Report No. AQS 21678/TR Rev. B 2. O LS Type EA-180 a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Pa r . 8.1. 3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D
- 4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79
- 5. Tech . Spec. 3.6-2 1 17-A L1-1-80
i SCEWS No. 17-A 37 TER No.
' Date: 8/21/81 i
O EQUIPMENT ENVIRONMENTAL QCALIFICATION 1 SER/TER REVIEW , Millstone Unit 2 , Docket No. 50-336 I) Summary of new information on SCEW sheet. l 4 None i II) Response to SER concerns. (A) ] i Refer to description of surveillance and preventive maintenance program
'r contained in body of submittal. ;
III) Response to TER concerns. !C:) Same as II. k IV) Proposed corrective action and schedule. ' Equipment will be incorporated into plant surveillance and preventive maintenance program, i l ! V) Justification for continued operation. I Not applicable i. O f 4 L-
O Facil : Millstone Nuclear Pr. Sta. O o
- " nit
- Two SYSTEM COMPONENT ' EVALUATIOt1 WORK SIIEET Docket: 50-33G
~ '
i 1 DOCUMENTATIO!1 REF* QUAL. OUTSTA!. DING EQU ;
- MENT DESCRIPTION ' ENVIRON!iENT
- l' METIIOD ITEMS Parameter Spec. Qual. Spec. Qual.
Approx. 5 System: Note 1. Operatin9 Sec. Fo l . Cont ir.uous 2 1.a) Simultaneous Plsnt ID No.: liv-? ? 30 Time lowing a Test liv-9125. CH 506, !!V-9151 inca. Compon'nt: Sc i enoid Temperature Profile 18 Profile 10 S imul t aneo u-5' Operatri Valves (OF) D ; 1.o) Test Manufacture: ASCO Pressure Pro file 19 Proffle 10 Simul t ar.cous (PSIA) D 1.b) Test Model Number: Relative 100 100 D 1.c) Simultaneous NP-206-381-6F liumidity(%) Test Function: Pilot Valves
! for LRR 4 3.1, GR-11.1, Chemical Simultaneous I CH-506, SSP-16.1 Spray 2400 PPri a F 1.d) Test Accuracy: Not Required Boron l
Radiation 1.5 x 108 R 2 x 108 R K 1.e) Sequential Service: Containment Test Isolation Incation: Containment Aging Req. maint. [ \ El. 3'-0", 3'-6", 8'-6", Sequential performed PDL Test every 3 yrs 40 Years ,4.4 Years 1 , 2'-6" i Flood Level Elev:(-)14'4" NA NA NA NA NA Above Flood Level: Yes X Sulnergence Mn
- Documentation
References:
Notes: 1
- 1. LRR-Clean Liould Radwaste System
- 1. ASCO Test Report No. AQS 21678/TR Rev. B GR-Gaseous Radwaste System a) Appendix A Par. 5 b) Appendix A Fig. 9.2 CH-Chemical 6 Volume Control System c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.l. 3 SSP-Drain System t c) Appendix D 2. Originally installed valves were replaced during
- 2. Tech. Spec. lable 3.6-2 October, 1979 outage 1 3. SMLS Type EA-740 11-1-80 19-A
.-__= . _ _ -. . . .. - _ .- - - - .-
1 I9-^ SCEWS No. TER No. Is i' Date: 8/21/81 O EQUIPMDiT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 ) l
- 1) Sumary of new inf ormation on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. t IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O 1 e -,-,y~ - , , , - -e, o w ., --m -, -,-4, w,- e ,,,-.,e,--- -,-,e--,,--m.,- . , , , , , , , , --eww-- +,,-we,- ve,r-- , , - - - , . , , - - - , - ,- ~ - - - , - - -
O Facil ; Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 1 EQUIPMENT DESCRIPTION ENVIROMMENT DOCUMENTATION REF* QUAL. OUTSTANDING METilOD ITEMS Parameter Spec. Qual. Spec. Qual. _ Approx. 3 System: Reactor Coolant Operating Sec. Fol - Continuous 4 3.a) Simultaneous Plant ID No. :llV--1064, Time lowing .est HV-1062, HV-1060 a loc.i . Component: Solenoid TemperatureProfile 18 Pro f il e 10 3.b) Simultaneoun Operated Valves (3F) D Test Manufacture: ASCO Pressure Profile 19 Profile 10 3.b) Simultaneoun (PSIA) Test D Model Number: Valve Type Relative 100 100 D 3.c) Simultaneoun 206-381-3F Humidity (%) Test Function: Piloc Valves for RC-001, RC-002,RC-003 Chemical 3.d) Simultaneoun Spray 2400 PPM B F Test Accuracy: Not Required Boron Service: R C Sample Valves Radiation 1.5 x 10 8 R 2 x 10 8 R K 3.e) Sequential Test Location: Containment Aging Req . maint. Sequential performed 40 Years 4.4 Years PDL 3 Test every 3 yrs. Flood Level Elev:(-)14'4" Above Flood Level: Yes Submergence nn X NO 5
- Documentation
References:
Notes:
- 1. 2. 1. Originally installed valves were replaced during
- 3. ASCO Test Report No. AQS 21678/TR Rev. B October, 1979 outage a) Appendix A Par. 5 b) Appendix A Fig. 9.2 2. SMLS Type EA-740 c) Appendix A Par. 8.1.3 .1) Appendix A Par. 9.4.2.4.3 e) Appendix D
- 4. Tech. Spec. Table 3-6-2
- 5. R.K. McCarthy letter to file dated 9-29-8C GEE-80-710 20-A 11-1-80
l SCEWS No. 20-A TER No. I9 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable , O
O
' Tci' y: Millstone Nuclear Pr. Sta.
o o Unit: Two SYSTEM COMPONrNT EVALUATION WORK S!!EET Docket: 50-336 ENVIRONMENT DOCUMENTATIO!! REF* QUAL. OUTSTANDII:G EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Encl. Bldg. Fil trat f oroperating P Continuour. P 3.a) Simultaneous Test Plant ID No. :ltJ-8380, Time ilV-8 378 Component: Solenoid TemperatureProfile 18 Pro file 10 3.b) Simultaneous Operated Valves ( F) D Test Manufacture: ASCO Pressure Profi1e 19 Profile 10 3.b) Simultaneou , D Test (PSIA) J Model Number: Valve Type Relative 300 100 D 3.c) Simultaneou:: NP-8344 B58V Humidity (%) Test Function: Pilot Valves for EB-91, EB-100 Chemical i 3.d) Simultaneoun Spray 2400 PPM B F Test Accuracy: Not Required Boron Service: Hydrogen Purge Radiation 1.5 x8 10 R 2 x 108 R 4. 3.e) Sequential Valves Test Req . maint . IDcation: Containment Aging Sequential performed El. 38'-6" every 3 yrs. 40 Years 4.4 Years PDL 3 Test. Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: YesX Submergence No
- Documentation
References:
Notes:
- 1. 2. 1. Originally installed valves replaced during
- 3. ASCO Test Report No. AQS 21678/TR Rev. B October,1979 outage a) Appendix A Par. 5 b) Appendix A Fig. 9.2 2. SMLS Type EA-740 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D
- 4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79 11-1-80 21-A
f ' 21-A SCEWS No. TER No. 20 Date: 8/71/81 O EQUIPMENT DIVIRONMENTAL QUALIFICATION SER/TER REVIEW i Millstone Unit 2 Docket No. 50-336 9 I) Sutumary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. l 1 III) Response to TER concerns. 0 Same as II. i i IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O >-s --..n- ,n.-,-n,e-e.,,,,,,--v ,--,-,+,m,-a.- m-,.,,,-,ne, ,.n,- - --
- O O O Facil *
- Millstone Nuclear Pr. Sta.
, Unit: Two SYSTEM COMPONENT EVALUATION WORK SilEET , Docket: 50-336 EQUIPMENT DESCRIPTION ENVIPO!! MENT DOCUMENTATION REF* QUAL. OUTSTA!! DING 3 i EE Sil 40(S1614) 68(S1634) METilOD ITEMS
- 66(S1624) 70(S1644) Parameter Spec. Qual. Spec. Qual.
System: Safety .njection Operating Note 1. Note 1. Note 1. Note 1. Note 1. I Plant ID No.:SI 614, S1 Time 624, SI 634, SI 644 Component: Valve Motor Temperature Profile 18 Profile 11 4.h) Simul t aneote Operators FF) D Test Manufacture: Limitorque Pressure Profile 19 Profile 11A Simultaneous 1 (PSIA) D 4.f) Test i ! Model Number: Serial Nos. Relat.ive 100 100 1. 4.a) Simultaneous ? 157040,157041,157042, ilumidity(%) Test j Function: 57Q43 For SI-612pN N SI-634
. Chemical Note 2. 4.d) Simultaneous SI-644 Spray 2400 PPM F Test Accuracy: Not Required Boron Service: SI Tank Isola- Radiation 1.5 x 108 R 2.04 x 108 ( K 4.c) Sequential tion Test
] i ~ Incation: Containment Aging
' Approx. Plant Sequential El. 19'-3" 40 Yrs. 40 Yrs. Desit1 4.e) Test Life i
l~ Flood Level Elev: (-)l4 '4" NA NA NA NA NA j Above Flood Level: Yes X , S' thnergence j - nn I
- Documentation
References:
Notes: j 1. Bechtel Technical Specs 7604-M-223A, 7604-E-40, 1. Not Applicabic. Valves are administrative 1y controlled j 7604-E-11B open (accident position) - Tech Spec 3 5-1A i 2. 2. Table 1, IEEE Std. 382, Page 12 3.
- 4. Limitorque Project Report 600456
- a) Par. 3.4.2 b) Fig. 6 c) Par. 4.3 d) Par. 4.4.2
- e) Par. 1.0 f) Fig. 5 23-A 11-1-80
SCEWS No. 23-A TER No. 21 Date: 6/21/81 . O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Sumcuiry of new inf ormation on SCEW sheet. i None 1 l II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. TER Had no concerns. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program, i l V) Justification for continued c,peration. Not applicable O
...-.-m_.-
7-, - -- ,..,_, - - _ ,m., ,-. ..,m.m_,-. . _ _ - , _ _ , , - - _ _ , , , . - , . _ , _ _ _ ,_ - , .
- a O v
Faci" /: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SilEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METi!OD ITEMS EE Sil 39(S1651) 62(S1652) Parameter Spec. Qual. Spec. Qual. 794 CY. System: Safety Injection Operating Note 1. Post Env. Note 1. 4.e) Seq uential Plant ID No. : SI 651, Time 4195 CY. Test SI-652 Total Component: Valve Motor TemperatureProfile 18 Pro file 11 Simultaneous , Operators ( F) D 4-M) Test Manufacture: Limitorque Pressure Profile 19 Profile 11 \ 4.b) Simi1taneous (PSIA) D Test Model Number: Serial Nos. Relative 100 100 1. 4.a) Simultaneous 4 155532, 155533 Humidity (%) Test I Function: Operators for l SI-651, SI-652 Chemical Note 2. 4.d) Simultaneous, Spray F Test 2400 PPM Accuracy: Not Required Boron Service: Shutdown Cooling Radiation 1.5 x 108 R 2.04 x 10 81t K 4.c) Sequential Isolation Valves Test I Incation: Containment Aging Approx. Plant Sequential El. O'-O", (-)1'-6" Design Test 40 Yrs. 40 Yrs. 4.f) 1 Life _. Flood Level Elev: (-) l4 ' 4 Above Flood Level: Yes X Submergence NA NA NA NA NA Nn
- Documentation Refereaces: Notes:
- 1. Bechtel Technical Specs. 7604-M-223A, 1. Valves are interlocked to prevent opening during l
4 7604-E-40, 7604-E-11B operation (Ref. Logic Diagram 25203-28115, Sil 47).
- 2. Long Term Requirement for Boron Percipitation Prevention.
- 3. 2. Table 1, IEEE Std. 382, Page 12
- 4. Limitorque Project Report 600456 a) Par. 3.4.2 b) Fig. 6 c) Par. 4.3 d) Par. 4.4.2 e) Par. 3.6 f) Par. 1.0 g) Fig. 5 24-A 11-1-00
SCEWS No. '24-A _ TER No. 22 Date: 8/21/81 l EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW M111 stone Unit 2 Docket No. 50-336 I .
- 1) Summary of new information on SCEW sheet.
I J None II) Response to SER concerns. (A) i 1 3efer to description of surveillance and preventive maintenance program I contained in body of submittal. III) Response to TER concerns. ! TER had no concerns, i IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Je +;ification for continued operation. Not applicable O
p Facil *: Millstone Nuclear Pr. Sta. Unit: " to SYSTEM COMPONENP EVALUATION WORX SIIEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Safety injection Operating Within 5 Plant ID No.4 IlY618.628 Time Sec. After Continuous 2 1.a) Simultaneout 638,648 a Loca. Test Component: Solenoid Temperature Profile 18 Profile 10 1.b) Simultaneous D Test Operated Valves ( F) Manufacture: ASCO Pressure P ro f i l e 19 Profile 10 1.b) Simultaneous (PSIA) Test Model Number: Valve Types Relative 100 100 D 1.c) Simultaneous NP-206-381-6kF Humidity (%) Test function Pilot Valves for SI618,SI628,SI638 Chemical SI648 Spray 2400 PPM Simultaneous R F 1.d) Accuracy: Not Required Boron Test Service: Safety Injection Radiation Sequential Tank Test and Fil1 Valves 1.5 x 10 8 R 2 x 10 8 R K 1.e) Test Req. maint. Location: Containment Aging Sequential performed El. O'-0" 40 Years 4.4 Years PDL 1 Te c every 3 yrs , Flood Level Elev:(-)l4 '4" NA NA NA NA NA Above Flood Level: YesX Sulnergence nn f
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 of Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4. 3 e) Appendix D
- 2. Tech. Spec. Table 3.6-2 25-A 11-1-80
'-- -- _ _ . - =-- m. _ _ _ _ _ - - -- . _ .
I l i SCEWS No. 25-A 23 TER No. Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 L 1 I) Summary of new information on SCEW sheet. 1 1 None I II) Response to SER concerns. (A) l Refer te description of .arveillance and preventive niaintenance program i centained in body of submittal. III) Response to TER concerns. Same as II. l IV) Proposed corrective action and schedule. ' Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable i O
1 O Faci r: Millstone Nuclear Pr. Sta. O O Unit: Two SYSTE*1 COMPONENT EVALUATION WORK SIIEET Docket: 50-136 ENVIRONMENT DOCUMENTATION PIF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MET!!OD ITEMS i _ Parameter Spec. Qual. Spec. Qual. System: Reactor Coolant Operating Simultaneous Plant ID No.: PT-100X,Y Time :ontinuous Continuous 2 1 Test Component: Temperature ,-(, f i l e I Profile
- cressure 1
- ism i t t er (OF) 16, 18 318*F D 14 Simultaneou<
l Test Manufacture: Presst.re , 1 Foxboro (PSIA) Profile Profi1e Simultaneous 16, 19 90 PSI D 34 Test Model Number: E-11CM rielative i j Humidity (%) 100% Profile Simultaneous Function: Pressurizer 100% D 34 Test Beater Control Chemical S"" ] Spray 2 00 PPM summary i \ccident Monitoring F Be sht. 27A Accuracy: 10.25% F.S. "" Service: Pressurizer Radiation 8 K summary 1.5 x 10 R Pressure Monitoring sht. % Location: Containment Aging See j El. (-)5'-0" 40 yrs. P.D.L. summary sht. 27A i Flood Level Elev: I.-) l4 ' 1" NA NA NA NA NA Above Flood Level: Yer( Subnergence Nn ,
- Documentation
References:
Notes:
- 1. Foxboro Test Report Q9-6005
, 2. FTII FSAR Table 7.5.2 i
23 11-1-80 l
.- . - - _ . _ . - - _- .. . . = - _ . . . ._ _ - - . - -- . -
SCEWS Ns. 27-A TER No. 24 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION l SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new inf ormation on SCEW sheet. None II) Response to SER concerns. (PPN. R CS-SEN, A) .I 1 This equipment will be replaced with fully qualified devices. III) Respense to TER concerns. Same as 11. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Ref er to corresponding equipment summary sheet. O
SISMARY SHEET NO. 27A 27A SCEW SHEET NO. 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 2 PT-100X, 100Y; PRESSURIZER PRESSURE, CONTROL MEASUREMENT CHANNELS EQUIPMENT: I MANUFACTURER: FOXBORO Model E11GM S/N 2607021, 2602022 i QUALIFICATION DISCREPANCY: These components lack documented qualification concerning their resistance to chemical spray, radiation and time / temperature aging. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: f] PT-100Y provides signal input for the post accident monitoring, subcoolino, margin monitor. Both these conponents initiate control signals which automatically energize or de-energize pressurizer heaters on a low or high pressurizer pressure condition. These components also provide control room pressurizer pressure indication. The poet accident subcooling margin monitor, will alarm a pressure input f ailure which indicates to the operator that this system should not ' e used for any safety related function. The automatic control of pressurizer heaters is a function which can be accomplished manually from the control room. An alternate method for determining primary plant pressure is provided by charging pump discharge pressure, and these components are not required for mitigation of a Chapter 15 Design Basis Event. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. O v
o : Millstone Nuclear Pr. Sta. o o 5'aci? Unit: Two SYSTEM COMPONEhf EVAT-UATION WORK SliEET Docket: 50-336 DbCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQtiTPMENT DESCRIPTION METHOD ITEMS 4 Parame'.er Spec. Qual. Spec. Qual. Simulta-Continuous Continuous 5 1 neous System: Main Steam Operating Test Plant ID No.: LT-5274 Time LT 5272 Temperature Profile 15 Component: Differential Profil 1 1,4 Simultaneous ( F) 17 Table D Pressure Transmitter 6A, 6B Test Manufa"ture: Pressurc Profile 15 . Foxboro (PLIA) Profile 19 17 Table D 1,4 Simultaneous ba, 6B Test Relative Profile 15 Model NumN r: E-13DM 17 Table 1,4 Simultaneous Humidity (%) D 100% est A, Function: Input fot 3 < element feetiater Chemical Profile 15 control accident monitorir spray,; 2400 prm 17 Table F 1,4 Simultaneous Accuracy: Boron 6A, 6B , G Test 0.5% Span Service: Steam Generator Radiation 8 Sequential Level Monitoring 1.5 x 108 R 2.2x10 R K 2,3 Test i 11 4 Location: Containment Aging 40 yrs. P.D.L* summary , El . 14 ' -6*' sht. 28A l 4 l Flood Level Elev:(-)l4'4" NA NA NA NA NA I Above Flood Level: Yes X Subnergence Mo
- Documentation RetFrences: Notes:
- 1. Foxboro Test Report T3-1013-MCA, Test of E-10 Series Differential t Gage Pressure Transmitters pgs. 7 & 8.
1 2. Foxboro Test Report T3-1097 Radiation Test of 410 Series amplifiers standard and radiation resistent pg. 3.
- 3. Foxboro Test Report T3-1068 Radiation Test of E-10 Series differential pressure transmitters of tb. MCA/RRW Type pg. 4.
- 4. FIRL Test Report F-C3635, " Maximum Credible Accident Environment Test of Four Transmitters Figurr 4
- 5. MPII FSAR Table 7.5.2 11-1-80 28A
-A SCEWS No.
TER No. 25 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUA1.IFICATION 4 SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEV sheet. None II) Response to SER concerns. (A) This equipment will be replaced with fu' y qualified devices. Ill) Response to TER concerns. Same as 11. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment sunnaary sheet . O
,----------.r, . -- ,. ,. --,- _ ., , ,... - .. nn.-------.-.--.. .,
SIDetARY SHEET NO. 28A SCEW SHEET NO.
^ .3 8-21-81 d , EQUIPMENT ENVIR0!OtENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDetARY MILLSTONE l'MIT 2 EQUIPMENT: STEAM CENERATOR LEVEL MONITORING, DIFFERENTIAL PRESSURE TRANSMITTERS LT-5272, 3274 MANUFACIURER: FOXBORO E-13DM S/N 3220857. 3220858 QUALIFICATION DISCREPANCY: Titre / temperature aging is not addressed in the manufacturer's qualification test reports.
SAFETY FUNCTION AND JUSTIFICATION hs FOR CONTINUED OPERATICN: These components provide signal input for the 3 element feedwater control system and control room steam generator level indication. The specification for these components identified 40 years as the desired desien life. Due to the present~ age of this equipment, and to the severity of the environmental test on this equipment in the as new condition, reasonable assurance is provided that the equipment will perform its design function. Due to the desarability of long term operability of this equipment and in conformance with cxisting license requirements, they will be replaced with fully qualified devited. Refer to Generic Replacerent Schedule 2. O
- - - - , , ,-----, ,..y rm -- , -,
.s. . --,
O O O Faci? : Millstone Nuclear Pr. Sta. SYSTEM COMPONE,NT EVALUATIOI4 WORK S!!EET Unit: Two i Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING r2UIPMENT DESCRIPTION MET!!OD ITEMS Parameter Spec. Qual. Spec. Qual. System: Main Steam vperating Continuous Continuous Simultaneous Plant ID No. : 1.T-1113A LT-ll23A Profile 15, Component: Temperature Differential Pressure (OF) Profile 18 17, Table D 1.4 Simultaneous Transmitter 6A, 6B Test Manufacture: Pressure Profile 15,' Profile 19 17 Table Simultaneous, D 1,4 Foxboro 6A, 6B Test Relative Profile 15 Model Number: E-13DB! " I* "" ""*
- Ilumidity (%) 100%
6A, 6B Test Function: R.P.S. Input Chemical Profile 15 6 Accident Monitoring Spray 2400 ppm Shlunem 4 DL F 1J Accuracy: Boron 6A, 6Be G Test Service: ' Steam Generator Radiation Sequential Level Monitoring 1.5 x 108 R 2.2x10 R. K 2,3 Test Incation: Containment Aging See El. 16'-0" 40 yrs. P.D.L. summary sht. 29A __ Flood Level Elev:(-)l4'4" NA NA NA Above Flood Level: YesX Sulznergence NA NA nn
- Documentation
References:
Notes:
- 1. Foxboro Test Report T3-1013. MCA, Test of E-10 Series Differential and Gage Pressure Transmitters pgs. 7 & 8.
- 2. Foxboro Test Report T3-lO97 Radiation Test of E-10 Series Amplifiers Standard and Radiation Resistant pg. 3.
- 3. Foxboro Test Report T3-1068 Radiation Test of E-10 Series Differential Pressure Transmitters of the MCA/RRW Type pg.
- 4. FIRL Test Report F-C3635 " Maximum Credible Accident Environment Test of Four Transmitters Figure 4.
- 5. MPII FSAR Table 7.5.2 20A 11-1-80
SCEWS No. j TER No. 26 j Date: 8/21/81
%.)
EQ'JIPMENT ENVIRONMDiTAL QUAI,IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. 1 None II) Response to SER concerns. (A) This equipment is to be replaced with fully qualified devices.
! \ III) Response to TER concerns.
1 Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. I O i l
SUletARY SHEET NO. 29A SCEW SHEET NO. 29A
. 8-21-81 m , EQUIPMENT ENVIRONMENTAL QUALIFICATION
( DISCREPANT EQUIPMENT SUlttARY MILLSTONE UNIT 2 EQUIPMENT: STEAM GENERATOR LEVEL MONITORING, DIFFERENTIAL PRESSURE TRANSMITTERS LTill3A, 1123A MANUFACTURER: FOXBORO E-12DM S/N 3220855, 3220856 QUALIFICATION DISCREPANCY: Time /tempe*ature aging is not addressed in the manufacturer's qualification test reports. g SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: These components provide RPS input for a eactor trip on low steam generator level, and control room steam generator 1avel indication. The specification for these components identified 40 years as the desired design life. Due to the present age of this equipment, and to the severity of the environmental test on this equipment in the as new condition, reasonable assurance is provided that the equipment will perform its design function. l l Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified cevices. Refer to Generic Replacement Schedule 2. l n
O Facil : Millstone Nuclear Pr. Sta. O- O Unit: Two SYSTEM COMPONt. fit EVALUATION WORK Sil"*"" Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METi!OD ITEMS Parameter Spec. Qual. Spec. Qual. System: Reactor Coolant Operating Jontinuous Continuous Simultaneous Plant ID No.: LT-110X Time 2 1 Test LT-110Y Component Temperature Profile 18 Differential Pressure (OF) 3188 F D Profile Simultaneous Transmitter 34 Test Manufacture: Pressure 1 (PSIA) Profile 19 Profile Simultaneoun 90 PSI D 34 Test 1 Model Number: E-13DH Relative Ilumidity (%) 100% Fur.ction : 100% D 34 Test PZR Heater Contro IChemical See 2 M summa Q g gi,g gimStCoggol Spray p Accuracy: 0.5% Span Service: Pressurizer Radiation See level monitoring 1.5 x 10 8 R K summary sht. 30A Incation: Containment Aging See El. (-)5'-0" 40 years P.D.L summary sht. 30A
- Flood Level Elev:(-)l4'4" ^ ^ ^
Above Flood Level: YesX Submergence un
- Documentation Re.'srences: Notes:
- 1. Foxboro Test T?> ort Q9-6005
- 2. MPli FSAR Tab. 7.5.2 11-1-80 30-A
SCEWS Ns. 30-A TER No. 47 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 l . i) Sumary of new inf ormation on SCEW sheet. s None 1 i II) Response to SER concerns. (R, CS-SEN, A) This equipment is to be replaced with fully qualified devices. i l III) Response to TER concerns. Same as 11. I ! IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. 1 l l i l O
SUDetARY SHEET NO. 30A SCEW SHEET NO. 30A N
- 8-21-81 (d , EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT Supe (ARY MILLSTONE UNIT 2 EQUIPMENT: Pressurizer level pontrol measurement channels) LT-110X, 110Y differential pressure transmitters MANUFACHIRER: FOXBORO E13DH S/N 2648245, 2648246 QUALIFICATION DISCREPANCY: These components lack documented qualification concerning their resistance to chemical spray, radiation and time / temperature aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment provides, charging pump control circuit input which de-energizes all but one charging pump on a high pressurizer level condition, and control room indication. These components also provide signals which energize or de-energize all pressurizer heaters on a high cr low-low level condition respectively. A low pressurizer level signal from these components also provides a backup signal to start all charging pumps. This equipment provides control signals only and in not required for mitigation of a Chapter 15 Design Basis Event. The control functions described above can be manually performed from the control room in the eve:nt of a worse case component failure. l I ( Due to the desirability of long term operability of this equipment and in i conformance with existing license requirements, they will be replaced with l fully cualified devices. Refer to Generic Reolacement Schedule 2. l O
G
) p)
L. ( S. V Faci? *: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM cot 1PONu1T EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTJ.NDING EQUIPMENT DESCRIPTION EINIPO!c1ENT METilOD ITEMS Parameter Spec. Qual. Spec. Qual. Continuous Conti,uous simultaneous System: Main Steam Operating Tiue 2 I Test Plant ID No. :PT-1013 A, B, D PT 1023 A,B,C,D C'omponent C : Temperature 1 Pressure Transmitter ( F) Proflie 18 Profile Simultaneous 318"F D 34 Tst Manufacture: Pressure Profile 19 1 Foxboro (PSIA) Profile Simultaneous 90 PSI D 34 Tgge 1 "d Relative Profile Simultaneous E-11 Humidity (%) 100% 34 Test 100% D
- See ESAS & RPS Chemical 2400 PPM
& Accident Monitoring Spray F Boron s. 3A Accuracy: 0.5% Span See Service: Steam Generator Radiation 8 s um ary Presst.re Monitoring 1.5 x 10 R K sht. 31A See Location: Containment Aging 40 yrs. P.D.L. summary El. 16'-O" sht. 31A Flood Level Elev: (-)14 '4" NA NA NA NA tc A Above Flood Level: Yes X Sulnergence Mo
- Documentation
References:
Notes:
- 1. Foxboro Test Report Q9-6005
- 2. MPII FSAR Table 7.5.2 11-1-80 31-A
SCEWS ND. _ 31-A 27 TER No. Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SEP concerns. (R, CS-SEN, RPN, A) This equipment will be replaced with fully qualifieddevices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. O J
'l
SUDMARY SHEET NO. 31A SCEW SHEET NO.
, 8-21-81 g , EQUIPMENT ENVIRONMENTAL QUALII'ICATION
%) DISCREPANT EQUIPMENT SUICiARY MILLSTONE UNIT 2 EQUII"AENT: STEAM CENERATOR PRESSURE (PROTECTIVE MEASUREMENTS CHANJELS) PT-1013/1023 A, B, C, D MANUFACITIRER: Foxboro E-11 l'ressure Transmitter S/No's 2602030, 2602031, 2602322, 2602033, 2602034, 2602035, 2602036, 2602037 QUALIFICATION DISCREPANCY: This equipment lacks documented qualification concerning their resistance to chemical spray, radiation and time / temperature aging. k SAFETY FUNCTION AND JUSTIFICATION FOR CONTIKUED OPERATION: f~
) These components provide the initiating signal for a reactor trip on a low steam generator pressure condition. These instruments also provide input signals for engineered safety features actuation of main steam and faedwater line isolation on a low steam generator pressure condition (main steam line break). The trip delay time for the reactor trip is 0.9 seconds in accordance with Tech. Spec. requirements. The trip dalay time is defined as the elapsed time between the time when the set point condition exists at the sensor and the time when the trip breakers are open for the CEA hold coils. The method of cable termination of these components precludes the possibility of admission of steam or fluid to the component internals during a steam line break. These components are subject to a borated water spray due to initiation of containment spray caused by a high containment pressure condition, but not before sufficient time has elapsed (0.9 seconds) for these components to per form their intended functions; reactor trin.
mainsteam and feedwater isolation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedele 2. s.
O Paci) : Millstone Nuclear Pr. Sta. o o SYSTEM COMPONt:;NT EVALUATION WORK SIIEET Unit: Two Dceket: 50-336 DOCUMENTATION PIF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIPOMMENT METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. System: React or Coolant Operating Continuous Continuous 2 1 Simultaneous Plant ID No. : PT102 A, B. Time Test C,D 1 Component: Temperature Profile Simultaneou ; Pressure Transmitter ( F) Profile 16 318,F 18 D 34 Test 1 Manufacture: Pressure Profile 16 Profile Foxboro (PSIA) 19 90 PSI D 34 Simultaneou ; Toet 1 Model Number: Fel.ative E-ll Humidity (%) 100% 100% D Profile Simultaneou ; est Function: ESAS & Reactor bee emical Protective System and , Accident Monitoring' P Y F sht. 32A Boron Accuracy: See Service: Pressurizer Radiation summary pressure monitoring 1.5 x 108 R K sht. 32A See Incation: Containment Aging sumary El. 7'-0" 40 yrs. P.D.L. sht. 32A Flood Level Elev:(-)l4'4" A A NA Above Flood Level: Yes X Submergence Nn
- Documentation
References:
Notes:
- 1. Foxboro Test Report Q9-6005
- 2. MPIl FSAR Table 7.5.2 11-1-80 32A
SCEWS No. 32-A TER No. 28 4 Date: 8/21/81 O EQt'IPMENT ENVIRONMCITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new inf ormation on SCEW sheet. None II) Response to SER cencerns. (R CS-SEN, RPN, A) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as 11. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Ref er to correspunding equipment summary sheet.
- O j
. . , . . - . . . . - - . . - , . - . , , - - . , - - , - - - - . , , , , - , , . - . . ~ - - . , . , . . - . - , . - . . , , . , , - , , . . - - . . , - , - , , , . . - , .
SIRGIARY SEEET NO. 32A SCEW SHEET NO. 32A 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUtetARY MILLSTONE UNIT 2 PRESSURIZER PRESSURE (SAFETY MEASUREMENT CHANNELS) PT-102A, B, C, D EQUIPMENT: MANUFACTURER: Foxboro E-11 Pressure Transmitters S/N 2602023, 2602024, 2602025, 2602026 QUALIFICATION DISCREPANC7: This equipment lacks documented qualification concerning their resistance to chemical spray, radiation and time / temperature aging. ( SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: These components provide the initiating signal for a reactor trip due to a high pressurizer pressure condition. The trip delay time for this function is 0.9 second in accordance with technical specification requirements. When a low pressurizer pressure condition exists these instruments provide input signals for engineered safety features actuation of ECCS, containment isolation and enclosure building filtration. Component location and the cable termination method preclude the possibility of the rapid admission of steam or fluid to the component internals during a LOCA. These components are required to mitigate the consequences of a LOCA. Their operability requirements ends within the first few seconds of the accident, and as such receives only a fraction of the LOCA radiation dose prior to operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. l V
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Fr.cli ): 1stona Nuclear P . Sts. I Unit Two SYSTEM COMPONDFF E.. JATION WORK SHEET Docket: 50-336
=
ENVIRONMENT DOCUMEJrrATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS MEDIOL Parameter Spec. Qual. Spec. Qual. System Reactor Coolant Operating Sequential Plant ID No.: RC-422.414, Time Continuous Continuout 1 2 Test 415,416,417,423,424,425 Component: Solenoid Tamperature Simulta-Valves ( F) Profile 18 346'F D 2c neous Test , Manufacture VALCOR Pressure Simulta-(PSIA) Pro file 19 113PSIG D 2c neous Model Number: Test V526-6042-3A V526-604 3- 3A Relative Simult'a-Humidity (%) neous i Function: Reactor Head 100 100 D 2c Test . MOD ppm and Pressurizer ' Onemical Simulta-Venting SPray 2400 ppm .N[LD S 0, neous
' 22 F 2c Test Accuracy: N/A Boron Note 1 Service: Radiation Sequential j 1.5X108R 2X108R K 2b Test Incation: CTMT Aging Sequentla1 38 '6" elev. 40 years 40 years PDL 2a,2b Test Flood Issvel Elev(-)14'4" Above Flood Level: Yes X Suhnergence NA NA NA NA NA un
- Documentation
References:
Notes:
- 1. The solution consisted of 2,200 ppm boron as
- 1. NUREG 0578 item 2.1.9
- 2. Valcor Engineering Qualification Test Report boric acid (113B03 ) in solution with 0.064 QR52600-515 molar sodium thiosulfate (NA s O3 ) buffered
- a. Appendix I with sodium hydroxide (NAOH)2 2to make a ph of 10.5 at room temperature.
- b. Appendix III
- c. Appendix IV 34a 11-1-80
SCEWS ND. 34-A TER No. 29 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. 4 i l None I l II) Response to SER concerns. (A) l l Refer to description of surveillance and preventive maintenance program contained in body of submittal. 1 I III) Response to TER concerns. (h The IE Bulletin on Valcor valves is not applicable to the valves at Millstone 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
Fccili 1ston2 Nuclear Pr. Sta. , SYSTEM COMPONENT E JATION WORK SHEET Units Two Docket: 50-336 ENVIRONMENT DOCUMENTATION TIF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS ME' MOD Parameter Spec. Qual. Spec. Qual. _ , Systesa: Reactor Coolant Operating Plant ID No. : RC414.415, Time Sequential 416,417,422,423,424,425 Continuous Continuous 2 1 Test Simulta- ! Component: Electrical Temiperature Connector ( F) neous Profile 18 340*F D Profile 33 Test Simulta-Manufacture? LITTON Pressure (PSIA) neous i
- Model Number
- Profile 19 105PSIG D Profile 33 Test CIR06VI-20-15S Plug CIR02VI-20-15P Receptacle Relative Simulta-Humidity (t) neous 100 100 D Profile 33 Test Function: Electrical -
Simulta-Connector chemical Spray 2400ppn 3000 ppm neous Boron Boron F Ic Test Accuracy: N/A 8 Service: RCS Venting Radiation Sequential Solenoid Valves 1.5X108R 2X108 R K la Test Incation: CTMT Aging 38'6" Sequential 40 years 40 years PDL lb Test Flood Imvel Elev:(-)14'4" NA NA NA NA NA Above Flood Level: Yes X Submergence un
- Documentation
References:
Notes:
- 1. Qualification Test of Electrical Connectors under A simulated LOCA/DBE be sequential exposure to environments of thermal aging, background radiation, containment pressurization, vibration, radiation (accident level), steam and chemical spray.
- 2. SUREG 0578 item 2.1.9
- a. Appendix B b. Paragraph 5.1 and 5.2
- c. Paragraph 5.6 35a 11-1-80
SCEWS N3. 35-A TER No. 30 Date: 8/21/81 O EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refertodes[riptionofsurveillanceandpreventiv-maintenanceprogram contained in body of submittal, t III) Response to TER concerns. O Scews 35A, Reference I was provided by Litton as applicable to the Millstone Unit 2 connectors. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable i I 1 ()
Fccil : illstons Nuclccr Pr. Sta. ( [ Unit: Two SYSTEM COMPONENT E...allATION WOR % SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDIMG EQUIPMENT DESCRIPTION ME'ntOD ITEMS Parameter Spec. Qual. Spec. Qual. Simulta-Systems Contaisiment Operating neous Plant ID No.: ED3.ED8.ED9 Time Continuous Continuous 1. 2.c) Test WD3.WD8,WD9 Component: Instrumentation Temperature Simulta-Electrical Penetrations (OF) Profile Profile D. 2.d) neous 18 38 Test Manufacture: COSAX Pressure Simulta-(PSIA) Profile Profile neous Model Number: 7852-10000 19 38 D. 2.d) Test Relative Simulta-Humidity (%) neous Function: Maintain elec- 100 100 1. 2.d) Test . trical continuity through cianical Simulta-the cont. struct. Spray 2400 PPM 6200 PPM neous l Accuracy: Not required Boron Boron F. 2.e) Test Service: Various instru- Radiation Sequential mentation circuits 9.4 x 10 6 R 2.0 x 10 8R M.
.b) Test Incation: Containment Aging Plant EL 14'6" Design Sequential 40 Yrs. > 40 Yrs. Life 2.a) Test Flood Ievel Elev:(-)14'4" Above Flood Imvel: Yes X Sulmergence NA NA NA NA NA un
- Doc e ntation
References:
Notes _:
- 1. NUSCO Specificat ion SP-GEE.-45
- 2. CONAX Qualification Test Report IPS 556.1 a) Par. 5.6.2. 3 Page 13 b) Par. 5.6.1 Page 11 c) Par. 5.8.1.1 Page 21 d) Par. 5.8 Page 21 e) Par. 5.8.1.2 Page 23 h
36A 11-1-80
SCEWS N3. 36-A TER No. 31 Date: 8/21/81 O EQUIPMENT DiVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns.(A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. (:) Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis, i i IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O v l
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Fccil t ,: (3 llctono Nucl =r Pr. Sta. v Units Two SYSTEM . UATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS MEnlOD Parameter Spec. Qual. Spec. Qual. System Simulta-System: Rad. Monitoring ' Operating Design neous Plant ID No.: ZlRM8240/ Time Continuous Continuous (P.A.M.) 1.a) Test B,C - Z2RM8241/B,C Simulta-Component: Coaxial cable Temperature SEE neous Profile 18 Profile 39 D 1.a) Test NOTE I Manufacture: Pressure Simulta-Rockbestos Co. (PSIA) neous Model Number : RSS 6-104 Profile 19 Profile 39 D 1.a) Test Design Simulta-Relative Req ui re- neous Humidity (%)
. wn .a est ,
Function: Rad .. m i to r in g - cab 1Ing ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous
' Boron Boron F 1.a) Test Accuracy: Not required Service: Low level Radiation Sequential signal circuits 1.5 x 10 8 R 2 x 10 8R K,L 1.b) Test Incation: Containment Aging Plant Design Sequential 40 Yrs. 40 Yrs. Life 1.c) Test Flood Level Elev:(-)14'4" Above Flood Ievel: Yes X Submergence NA NA NA NA NA
- Documentation
References:
, Notes: 1. Vendor has advised of an anomaly
- 1. Rockbestos report, " Qualification of fi"cwall Ill in temperature qualification which coaxial constructions dated January 18, 1978". may affect this equipment. An investi-a) Page 2, Par. IV gation is presently li progress to determine b) Isomedix report dated December 27, 1977 app!icability and effect on this equipment.
c) Page 2, Par. II 37-A 8-21-t$1
SCEWS NN. 37-A TER No. 32 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Sum =ary of new information on SCEW sheet. Adkd nets 1. II) Response to SER concerns. (A) ! Refer to description of surveillance and preventive maintenance program ntained in body of submittal. III) Response to TER concerns. Qualified life is greater then or equal to the plant design life. i The above referenced surveillance program will periodically verify the aging analysis, i IV) Proposed corrective action and schedule. Cable te he replaced with a qualified equivalent. Repl aceme.- t to be supplied by Ge.eral Atomic and Bcekbertos Companies as soon as it 14 4:vailable. V) Justification for continued operation. Not applicable , syst em is not required to be operational uritil 1-1 82. O
FCcil Unit
.llcton3 Nuclear Pr. Sta. g ,
SYSTEM COMPONENT %. JJATION WORK SHEET f') U Dockst 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITF#.S Parameter Spec. Qual. Spec. Qual. Svstem Simulta-SystemPost Accident Mon. Operating D[ sign neous Plant ID No.: T356, T357 Time Continuous Continuous (P.A.M.) 1.a) Test Component: Terminal block Temperature Simulta-( F) neous Profile 18 Profile 40 3 1.a) Test Manufacture: WeidmulIer Pressure Simulta-Terminations Inc. (PSIA) neous Model Number: Type SAK4 Profile 19 Profile 40 D 1.a) Test Relative Design Simulta-Humidity (%) Require- neous Function: Termination of 100 100 ment 1.a) Test ,
~
monitoring circuits ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous Accuracy: Boron Boron F 1.a) Test Service: Containment sump Radiation Sequential 1.5 x 10 8 R 2.07x10 8R K,L 1.b) Test Incation: Containnant Aging Plant Design Sequential 40 Yrs. '40 Yrs. Life 1.c),2. Test Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Suhnergence NA NA NA NA NA un j
- Documentation
References:
Notes:
- 1. FRC final report F-C5205- 3 a) Page 4-7 id ^ppendix C c) Appendix B
- 2. Weidmuller letter dated June 10, 1980 38-A 11-1-80
SCEWS No. 38-A TER No. 33 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUAL.IFICATION i SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program
- contained in body of submittal.
l III) Response to TER concerns.
- FRC should review documentation.
IV) Proposed corrective action and schedule. , Equipment will be incorporated into plant surveillance and preventive j maintenance program. V) Justification for continued operation. l l Not applicable r l l l l l .- . - . . _ . _ _ _._ __ _ . _ _ . _ . . . . _ _ _ _ _ -
f") pm V ~ Facil : Millstone Nuclear Pr. Sta. SYSTEM COMPOt!!:;NT EVALUATION WORK SIIEET Unit: Two Docket: 50-336 4 MENTATION RE7* QUAL. OUTSTANDING ENVIRON?iENT EQUIPMENT DESCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. Passive Contiau- Device See System: Various Operating Time ous Continuous 1. Qualified Qual. Plant ID No.: By Design Box Component: Electri al Temperature Simultaneous Profile 3., A., I. Penetration Term. ( F) Test 26 Note 1. 2. Blocks Manufacture: General Pressure Electric Company (psia) 3., A., I. ' Simultaneous II Note 1. 2. Test Model Number: CR-151 Relative Simultaneous nst 100 100 1. 2. Function: To Terminate Connections to Elec- ' Chemical Spray NA NA NA NA NA trical Penetrations Accuracy: Not Required Service: Radiation NA NA NA NA NA Various Incation: Enclosure Agin9 Plant 40 yrs. 12x10 6 yr Design 4 Arrhanius Bldg. EL 14'6" Analysis Zone A25, A?6 Life Flood Level Elev: Above Flood Level: Yes Sulunergence un
- Documentation
References:
Notes: 1. Qualification Profiles from Doc. Ref. 2.
- 1. Bechtel Tech. Spec. 7604-E-34 320 340 320 260 Temp F 260
- 2. GE Ltrs. G-EH-8-16 Dated 2/2/78 75 103 75 21 G-EH-9-141 Dated 10/18/79 Press PSIG 21 100 100 100 100 100 Term. Block Loca Test Forwarded by C.E. Ltr., RH%
R. F. Thibault to R. DeRosa Dated 12/14/79 Duration 1 5 Days 1.5 Hrs. 3 Hrs. 4.5 Hrs. 8 Days
- 3. FSAR Amendment 17
- 4. Wyle Report 17436-46 dated 2/3/81 8-21-81 1-B
SCEWS No. 1-B
; TER No. 34 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I
I) Summary of new information on SCEW sheet. Aging Analysis utilizing Arrhenius Methodology completes qualification. II) Response to SER concerns. SER lists this item in both Appendix B and Appendix C. Terminal Blocks outside Containment are not in a high radiologii 1 zone. I I III) Response to TER concerns. FRC should review the documentation. 1 IV) Proposed corrective action and schedule. Refer to description of plant sutveillance and preventive I maintenance program. l l t l V) Justification for continued operation. l Niit applicable. i I t 4 1 i
. - __-,.m,_ ...m.. _ , _ .,_ , , , , ,_ . _ , , . - . . . .,,,,_m._._m. . _ - . . . ~ . . _._r..,,_ ,y.. , _.
____m ,, -. y. . - ._.. ,-..
O O- O Facil : Millstone Nuclear Pr. Sta. Unit: en) SYSTEM COMPONErd EVALUATION WCRK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Passive V System: Electric Plant ID No.: Operating
.ime Continu-ously Contin-uously 1.
Design bd Box 4. , Componei.c : 5000 V Temperature Simulta-Power Cable ( F) Profile Profile A neous 24 25 2.a) Test Manufacture: General Pressure Profile 35 Simulta-Cable Corp. (PSIA) Note 1) A neous a H Table 3 2.a) Test Simulta-Model Number: EPR insul. Relative Hypalon Jacket Humidity (%) 100 100 1. 2.a) neous Function: Wireways Test for Medium Voltage chemical Motors & Power Sources Spray NA NA N/. NA NA Accuracy: Services Radiation Sequential 4160 V Systems 1x10 7R 5x10 7R 1. 2.a) Test Location: Aging "" 40 yrs. At least Various Plant Areas design 3 Analysis 40 yrs Outside Containment life i ! Flood Level Elev: Above Flood Level: Yes Submergence nn l
*Doctnaentation
References:
Notes: 1) No Safety Related 5000 V Cable in Areas
- 1. Bechtel 'Jechnical Spee. 7604-E-15 Outside Containment Subject to High
- 2. General Cable Corp. Report Dated 11/70 Temperature, i.e. 2610F or Higher a) Table 4
- 3. Wyle Laboratories letter in response reference:
174365-018 dated October 24, 1980 and Telecon dated October 29, 19 80 11-1-80 2-B
SCEWS Ns. 2-B TER No. 35 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUAL.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 ,
- 1) Summary of new information on SCEW sheet.
None II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. - Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O Facil : Millstone Nuclear Pr. Sta. O O
- Unit
- Two SYSTEM COMPONENT EVALUATION WORK SHEET
; Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.
Simulta-Systen: Electrical Operating Continu- Continuous 2.c) acous Plant ID No.: Time ous 1. Test Component: Control Temperature , Cable (OF) Profile 20 A, D Simultaneous Profile 3 2.a) Test i Manufacture: Pressure Ketite (psia) Note 1. Profile 3 A 2.a) Simultaneous Tour Model Number: Relative Fr Insul. Fr Jacket Humidity (%) 100 100 1. 2.a) Simultaneous Function: Wireways for Test Control and Low Level Chemical Pwr. Ckts. Spray NA NA NA NA NA Accuracy: Not Required Service: Padiation Various Control e,d Simultaneous Low Level Pwr. tx 1x108R 2x108R 1. 2.b) Test l Incation: Aging General Plant 40 yrs. Simulated 1. 3 Sequential Areas outside Contain- 40 Yrs. Test 4 ment Flood Level Elev: Above Flood Level: Yes Sulznergence un
,
- Documentation
References:
Notes: 1. Environmental pressure is less than
- 1. Bechtel Technical Spec. 7604-E-18 2PSIG for about 13 sec. This is insignificant.
l 2. Franklin Institute Report F-C4020 1 a) Fig. 1 4 b) Page 5-2 c) Page 6-1
- 5. Kerite Engineering Memorandum 178A, May 1, 1979 11-1-80 3-B
SCEW3 No. 3-B TER No. 36 Date: 8/21/81 EQU:? MENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW M111stose Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. .I I () III) Response to TER concerns. 1RC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not epplicable O
p C O h ( V 3 Faci" J: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SliEET Docket: 50-336 EINIRO!.? TENT LOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METilOD Parameter Spec. Qual. Spec. Qual. Simulta-System: Electric Operating Continu- Continuous ne us Plant ID No.: Time ous 1. 2.d) Test Component: Low Voltage Ten perature Power Cable t F) eProf ile 2 A, D Simultaneous Profi?e 20 2.a) Test Manufacture: Pressure Anaconda (psig) Profila 2 Simuitaneous Note 1. A 2.a) Test Model Number: Relative Simultaneous EPR Insul. CSPE Jacket Humidity (%) 100 100 '. 2.a) est Function: Wireways for Low Voltage Motors, Chemical D.C. Systems, Heaters, SP ray Simultaneous Accuracy: Etc. NA NA NA NA Test Not Required Service: 480 V, 120 VAC, Radiation Sequential 125 VDC Circums lx10 7 R 2x108R 1. 2.b) Test , Incation: General Plant Aging Areas Outside contain- 40 yrs. Simulated 1. 2.f) Sequential ment 40 Yrs. Test Flood Level Elev: Above Flood Level: Yes Subnergence na r
- Documentation
References:
Notes: 1. Environmental pressure is less than 2PSIC
- 1. Bechtel Technical Spec. 7604-E-17 for about 13 sec. This is insignificant.
- 2. FIRL Test Report F-C4350-3 a) Fig. 2 b) Appendix C c) Page 3-1 d) Page 3-3 f) Attachment Dated May,1977 4-B 11-1-80
SCEWS No. 4-B TER No. 17 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerrs. Refer to description of surveillance and preventive maintenan::e prograr contained in body of submittal. III) Response to TER concerns. FRC should review documentation. 4 IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillmace and preventive maintenance program. V) Justification for continued operation. i Not applicable t O 4
- , - - - . . , . _ - , - , _ _ , _ . . , , . _ _ _ _ . , - . . - _ _ . , _ _ . , . _ _ - . ~ . _ - - _ - - . _ . - _ _ , . _ . . , . . . . - - - , . . _ _ _ . _ - _ . . . . . _ . - _ . -
O Faci. /: Millstone Nuclear Pr. Sta. O o Unit: Two SYSTEM COMPONisNT EVALUATION WORK SIIEET Docket: 50-336 EIN1RONMENT
- DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METilOD ITEMS Parameter Spec. Qual. Spec. Qual. _,
System: Instrumentation Operating Continu- Continu-Time ous ous 1. 2.a) Note 1 Plant ID No.: Component: Instrument Temperature U ie (op) Profile 20 Profile 4 A,D Simultaneout 2.b) Test
- Manufacture: Pressure Rockbestos Co. (psIn}
Note 2. Profile 4 A Simultaneous (Cerro)' 2.b) Test
- Model Number: Relative Simultaneous XLPE Insul-Neoprene Humidity (%) 100 100 1. 2.c)
Jacket Test
- Function:
Wireways for In;tru- - Chemical NA NA NA NA mentation Ckts Spray NA Accuracy: Not Required Service: Radiation i General Instrumentation 8.60x10 6R 2x100R C,L 2.d) Simultaneous Test
- Location: General Plant Aging Simulated Sequential Areas Outside Contain- 40 yrs.
40 yrs. 1. 2.e) Test ment i Flood Level Elev: Above Flood Level: Yes Sulnergence , nn
- Documentation
References:
Notes: _,
- 1. Bechtel Technical Spec 7604-E-19A
- Insulation Only*
- 2. Cerro Cert. Report Dated 2/1/77 1. Cable involves low current only. Continuous a) Page 1. operation is inherent.
b) Loca Profile Page 8 2. Environmental pressure is less than 2PSIG for c) Page 4. Par. V about 13 sec. This is insignificant. d) Page 3. Par. V e) Page 2 11-1-80 5-B
SCEWS No. 5-B TER No. 38 Late: 8/21/81 ('T U EQUIPMENT ENVIRONMENTAL QUAL.IPICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None l II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) R=.iponse to TER concerns. Qualified life is greater tl.in or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable
/"
Facilit! 11cton2 Nuclear Pr. Stn. / SYSTEM COMPONENT EV..JATION WORK SHEET U] Unit Two Docket: 50-336 1 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION ME'n{OD ITEMS Parameter Spec. Qual. Spec. Qual. _, System: Instrumentation Operating Continuous Continuout 1. 2.c) 3imultaneous Time fest Plant ID No.. i t Temperature Component gns t rument goF) Profile A,D 2.a) Simultaneous ! Profile Cable 20 3 Test l Pressure ' Manufacture: Kerite (PSIA) Note Profile A 2.a) Simultaneous 3 Test Model Number: 600 V 1 Relative 100 100 1. 2.a) Simultaneous
- Humidity (%) Test
- Function: Wirewayr, for instrumentation circuits ' diamical Spray N/A N/A N/A N/A N/A Accuracy: Not required General 6 8 C,L 2.b) Simultaneous Service: Radiation 8.60 X 10 2 X 10 R Test instrumentation R 1
Incation: General plant Aging 3. 4 areas outside the ntat. 40 yrs. Simulated 1. Sequential 40 yrs < Test l Flood IAvel Elev: Above Flood Level: Yes Submergence un
' Documentation
References:
Notes:
- 1. NUSCO Standard Specificatin for instrument cable 1. Env iroamental pressure is less than 2 PSIG for abcut 13 600 volts SP-GEE-14 seconds. This is insignificant.
- 2. FIRL Test Report F-C 4020-1 dated March 1975 a) Fig. I b) Page 5-2 c) Page 6-1
- 3. Kerite Engineering Memorandum 178A, May 1979 5-Ba 11/1/80
SCEWS N3. 5-B3 TER No. 39 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW M121 stone Unit 2 Docket No. 50-336 I) Summary e.f r.sw information on SCEW sheet. None II) Response to SER conceir.s. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER cone. erns. I ! FRC should review documentation. IV) Proposed corrective action and schedule. Equipment vill be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O 1 ( - . - - - . . - . . _ . _ _ . _ , . _
O Fac i." /s Milletane Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPON!z T EVALUATION WORK SIIEET Docket: 50-336 _ . m ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METI!OD ITEMS Parameter Spec. Qual. Spec. Qual. Must open 200 CY at System: Safety Injection Operating and stay 165 0F, Sequential Plant ID No.: SI613, Time open 100.% Ril 4. 3.e) Test SI625, SI635, SI645 Component: Valve Motor Temperature 2. Operators ( F) ll20 F max. Profile 12 A Simultaneous 3.d) rest Manufacture: Pressure 2. Limitorque (PSIA) Profile 12 A Simultaneous H 3.d) Test Model Number: Operator Relative 1., 2. S/N 137101, 137102, liumidity (s) g Simultaneous Function: 137103, 137104 1( 100 3.a) Test Operators for SI615, Chemical SI625, SI635, SI645 Spray NA NA NA NA NA Accuracy: Not Required - Service: Radiation LPSI Flow 4.80x10 6 R 2.04x10 8R C,L Sequential 3.c) Test Incation: Encl. Bldg. Aging Plant EL.(-)5'0", W. Pipe Simulated Design Sequential Pent. Rm. Note 1 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev: Above Flood Ievel: Yes Submergence Nn
- Documentation
References:
Notes: 1. ZONE
- 1. Bechtel Technical Spec. 7604-M-780 SI 615 A18
- 2. FSAR Ammendment 17 SI 625 A18
- 3. Limitorque Test Report B0003. 11-13-74 to 1-23-75 SI 635 A18 a) Par. 2.1.1 SI 645 A18 b) Par. 5.0 c) Par. 2.3 d) Fig. I e) Par. 2.1.3 7-B
- 4. FSAR Sec. 6.3.3.1 & P & ID 25203-26015 11-1-80
SCEWS N). 7_n TER No. an Date: 8/21/d1 4 I O EQUIPMENT DIVIRONM5TAL QUALIFIMTION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. i None i I II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program ' contained in body of submittal. III) Response to TER concerns, j FRC should review documentation. l l IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O 4
. . , , _ , . . - . . . . , . . - , n ,- .- . - , . , . - - , , . . - . - ..m- e. -y. ~ , . _ _ - . - y --r,.---m ,,,----_.----.._m .-. .
O Facil : Millstone Nuclear Pr. Sta. O O Unit: Two SYSTEM COMPONENT EVALUATION WORK SiiEET > Docket: 50-336 ENVIPOr.HENT DOCUMENTATION PIF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METIIOD Parameter Spec. Qual. Spec. Qual. _ Must open 200 CY at System: Safety Injection Operating and stay 165 F, Sequential Plant ID No.: SI616, Time open 100% RH 4. 3. e) Test SI626, SI636, SI646 Component: Valve Motor Temperature 2. Operators ( F) ll20 F max. Profile 12 3 Simultaneoun 3.d) Test. Pressure 2-Manufacture: Limitorque (psyn) Profile 12 3 Simultaneous
!! 3.d) Test Model Number: Operator SA Relative 1., 2.
134075, 134077, 134079, Humidity (s) A simultaneou: Function: 134081 100 100 3.a) Test Operators for SI616, Chemical i SI626. SI636, S1646 Spraf NA NA NA NA NA Accuracy: Not Pequ ired . Service: Radiation 9 PSI Flow 4.80x106R 2.04x108R CL Sequential 3.c) Test Incation: Encl. Bldg. Aging Plant EL(-) S'0", W. Pipe Simulated Design Sequential Pent Rm. Note 1 40 Yrs. 40 Yrs. Life 3.b) Test Flood Ievel Blev: Above Flood Ievel: Yes Subnergence
% _n
- Documentation
References:
Notes: 1. ZONE
- 1. Bechtel Technical Spec. 7604-M-780 SI 616 A18
- 2. FSAR Ammendment 17 SI 626 A18
- 3. Limitorque iest Report B0003, ll-13-74 to 1-23-73 SI 636 A18 a) Par. 2.1.1 SI 646 A18 b) Par. 5.0
'c ) Par. 2.3 d) Fig. 1 e) Par. 2.1.3 8-B
- 4. FSAR Sec. 6. 3. 3.1,P & ID 25203-26015 11-1-80
SC NS N3. 8-B 1 TER No. 41 Date: S/21/81 l O EQUIPMENT UVIRONM ETAL QUALIFICATION SER/TER REVIEW Millstone 'Jnit 2 Docket No. 50-335 s I) Sutenary of new inf ormation on SCEW sheet. None II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation.
'V) Proposed corrective action and schedule.
i I Equipment will be incorporated into plant surveillance and preventive mrintenance program. V) Justification for continued operation. t i Not applicable O 1.- , _ , _ _ . _ , _ - - - , _ _ _ _ _ . . _ _ _ . _ . . . . _ . . _ . . _ . . _ , _ _ . . _ _ _ _ _ _ _ . _ . _ , _ _ _ _ _ , _ . . . , _ _ _ _ _ _ . _ _ , _ . _ , , _ _ _ _ _ _ _ . _
O Faci" y: Millstone Nuclear Pr. Sta. O o Unit: Two SYSTEM COMPONErvT EVALUATION WORK SHLET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS
- Parameter spec. Qual. ! ec. Qual.
1 System: Safety Injection Operating Must open 200 CY at Sequential Plant ID No.: SI617, Time and stty 165 "F Test lI627, SI637, SI647 _ open 100% RM 4. 3.e) Component: V*1ve Mozor Temperature 2. ( F) Simt1taneous Operator 1120 F max. Profile 12 3 3.d) Test 4-Manufacture: Pressure Limitorque (p3rg} H Profile a2 i Simultaneous A 3.d) Test Model Number: Operator .;*r4 Relative 1., 2. 1 134076, 134078, 134080 Humidity (%) Simultaneous Function: 13408: 100 100 A 3.a) Test Operators for SI617, Chemical i SI627, SI637, SI647 NA NA NA NA NA Spray Accuracy: Not Required i Service: Radiation HPSI Flow 4.80x10 6R 2.04xlG 0R CL Sequential 3.c Test Incation: Encl. Bldg. Aging Plant EL.(-) 5'0", W. Pipe Simulated Design Sequential Pent. Rm. Note 1 40 Yrs. 40 Yrs. Life 3.b) Test
< Flood IAvel Elev:
Above Flood TAvel: Yes Subnergence
- 1
- Documentation Peferences: Notes: 1. ZONE
- 1. Bechtel Technical Spec. 7604-M-780 SI 617 A18
- 2. FSAR Ammendment 17 SI 627 A18
- 3. Limitorque Test Report B0003. 11-13-74 to 1-23-75 SI 637 A18 a) Par. 2.1.1 S1 647 A18 b) Par. 5.0 c) Par. 2.3 d) Fig. 1 e) Par. 2.1.3
- 4. FSAR Sec. 6.3.3.1, P & ID 25203-26015 11-1-80 9_g
i SCEWS No. 9-B 4 TER No. 42A 1 1 Date: 8/21/81 O EQUIPMENT UVIRONM E TAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. I III) Response to TER concerns. l O FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plava surveillance and preventive i naintenance program. V) Justification for continued operation. Not applicable O
O Facil : Millstone Nuclear Pr. Sta. O O' Unit: Two SYSTEM COMPONENT EVALUATION WORK Si!EET Docket: 50-336 ENVIRON."rNT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METi!OD ITEMS Parameter Spec. Qual. Spec. Qual. , Operating NA 76.5 Sec. System: Chem. 5 Vol. Control Time Valve must Stroke 4. Sequentiaq Plant ID No.: HV2524 stav as is. Time 3.e) Test 2-Component: Valve Motor Temperature Simultaneous Operators ( F) 112 F max. Profile 11 3 3.c) Test Manufacture: Pressure Profile 13 2. Limitorque gpgy3) 11 3 Simultaneous 3.c) Test Operator I*' 2' Model N r: Relative 100 Simultaneous S/N 17 86 Ilumidity (%) 100 3 3.d) Test Function: Operator for CH-429 C'emical Sp.ay NA NA NA NA NA Accuracy: Not Rtqu ired i Service: Radiation Sequential Charging Pump 2.04x10 8R 4 l Discharge 6 1.65x10 R CL 3.a) Test Incation: Aging Plant Encl . Bldg. Design Sequential EL.(-) 5'0", W. Pipe 40 Yrs. Life Test 40 Yrs. Pent. Rm. Zone A18 3.b) Flood Ievel Elev: Above Flood Ievel: Yes Submergence nn
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-223A
- 2. FSAR Ammendment 17
- 3. Limitorque Test Report 600376A. 4/26/72 to 8/30/72 a) Par. 2.1 b) Appendix C, F-C3441 Par. 4.0 c) F-C3441 Fig. 3 d) F-C3441, Par. 3.2, Page 3-3 e) F-C3441, Par. 3.3.3 11-1-80
- 4. FSAR Fig. 9.2-2 10-B
SCEWS Ns. 10-B TER No. 42B Date: 8/21/81 EQUIPMENT ENVIRONMDiTAL QU11FICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance progrri i contained in body of submittal. III) Response to TER concerns. O FRC should review documentation which was obtained from 1.imitorque as applicable to these valves at Millstone Unit 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. 1 Not applicable O : _ . . , _ , . _ , ~ . , _ _ _ . - . . . - . . . _ _ _ _ . . _ , _ _ _ _ _ _ . - - . . _ , _ _ , _ _ . -
O Fcci f: Millstone Nuclear Pr. Sta. o o SYSTEM COMPONE,NT EVALUATION WORK SIIEET Unit: Two Docket: 50-336 i ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METI{OD Parameter Spec. Qual. Spec. Qual. _ , 1 NA System: React.-Bldg.CCW Operating Valve Must 76.5 Sec. Sequential Plant ID No.: Time Stay as is Stroke 4- 3.e) Test llV6096, ilV609$ Timo d Component: Valve Temperature 2. ' Motor Operators (OF) 112 F max. Profile 13 A Simultaneous 3.c) Test Pressure 2. I Manufacture: Limitorque (PSIA) Profile 13 Simultaneous
] A 3.c) Test Model Number: Operator S/N Relative 1., 2.
152851, 152849 Humidity (%) 100 100 A 3.d) simultaneous i Function: Operators Test for 2-RB30-1A, 2-PS30-1B Chemical Spray NA NA NA NA NA Accuracy: Not Required
; Service: Radiation RBCCW to RC Pumps 4.80x10 6R 2.04x10 0R C,L Sequential 3.a) Test Incation: Encl. Bldg. Aging Plant EL(-) 5'0" W. Pipe Design Sequential Pent. Rm Zone A18 40 Yrs. 40 Yrs. Life 3.b) Test
~
1 Flood Level Elev: Above Flood Level: Yes Submergence l l
- Documentation
References:
Notes: 4 1. Bechtel Technical Spec. 7604-M-223A
- 2. FSAR Ammendment 17
- 3. Limitorque Test Report 600376A 4/26/72 to 8/30/72
; a) Par. 2.1 i b) Appendix C , F-C3441 Par. 4.0 c) F-C 3441, Fig. 3 d) F-C 3441, Pa r. 3. 2, Page 3-3 4
e) F-C 3441, Par. 3.3.3 11-1-80 II~E
- 4. FSAR Table 9.4-2, Fig. 9.4-2
SCEWS N3. 11-B TER No. 42B Date: 8/21/81 EQUIPMENT ENVIRONMDITAL QUA1,1FICATION 4 SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation which was obtained from Limitorque as applicable to these valves at millstone Unit 2. IV) Proposed corrective action and schedule. l i l Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O Facil : Millstone Nuclear Pr. Sta. O o A Unit: Two SYSTEM COMPONENT EVALUATION WORK SilEET Docket: 50-336 s , ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _ NA System: React. Bldg. CCW Operating Valve Must 76.5 Sec. , Sequential
- Plant ID No.
- Time Stay as is Stroke 3.e) Tests HV6108, HV-6106 Time Component: Valve Temperature 2.
Motor Operators (OF) 112 F max. Profile 13 A Simultaneous 3.c) Test
- Manufacture
- Pressure 4
Limitorque (psyn} Profile 13 2.
}
A 3.c) Simultaneous Test Model Number: Operator Relative 1., 2. S/N 152850, 152848 Humidity (%) 100 100 A Simultaneous Function: 3.d) Test Operators for 2-RD37 -2A, Chemical 2-RB37-2B Spray NA NA NA NA NA Accuracy: Not Requ ired Service: Radiation RC Pump Oil Clg. Water Sequential 4 8 Disch. 4.80x106R 2.04x10 R C,L 3.a) Test Incation: Encl. Bldg. Aging Plant (-) 5 ' O " W. Pipe Design Sequential Pent. Rm. Zone A18 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev: Above Flood Imvel: Yes Subnergence Mn
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-223A
- 2. FSAR Ammendment 17
- 3. Limitorque Test Report 600376A 4/26/72 to 8/30/72 a) Par. 2.1 b) Appendix C , F-C3441 ;/ar. 4.0 c) F-C 3441, Fig. 3 d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3
- 4. FSAR Table 9.4-2, Fig. 9.4-2 11-1-80 12-B
_ . - . - _. _ _ =. - - -. ._. SCEWS No. 12-B TER No. 42B Date: 8/21/81 [ EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. > None II) Response to SER concerns.(A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation which was obtained from L'.mitorque as applicable to these valves at Millstone Unit 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
/
Faci: ': Millstone Nuclear Pr. Sta, Unit: Two SYSTEM COMPONENT EVALUATION WORK S!!EET Docket: 50-336 Note 1 MENTATION REF* QUAL. OUTSTANDING ENVARONMENT EQUIPMENT DESCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. . Qual. _ System: Safety Injection Operating NA 200 CY at Valve Must 165 F, 4. 3.e) Sequential Plant ID No.: S1653, Time Test SI654, S1655, S1656 Stay as is 100% RH 2* Component: Valve Motor Temperature Simultaneous Operators (or) 112 F inax. Profile 12 A 3.d) Test Manufacture: Pressure Limitorque 2. gp373) Simultaneous ig Profile 12 g 3.d) Test Operator S/N 1., 2.
- Relative Simultaneout Model 13408 f,umbe[d83, 13 134085, ilumidity(s)
A 134228 100 100 3.a) Test Function: Operators for SI653, Chemical SI654, SI655, SI656 Spray NA NA NA NA NA Agcuracy Not Hequ: ired 6 8 I N fu'mp Discharge 3. 33x10 R 2.04x10 R C,L Sequential 3.c) Test Bldg. EL Aging Plant
%atgpg,, Aux. Simulated Design Sequential Note 2 40 lirs. 40 Yrs. Life 3.b) Test Flood Level Elev Above Flood Level: Yes Submergence No i
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-780 1. SI653, SI654 must function in a radiation
, 2. FSAR Ammendment 17 (only) environment.
- 3. Limitorque Test Report B0003 11/13/74 to 1/23/75 2. ZONE a) Par. 2.1.1 SI 653 A3 b) Par. 5.0 S1 654 A3 c) Par. 2.3 SI 655 A2 d) Fig. 1 S1 656 A2 11-1-80 e) Par. 2.1.3
- 4. FSAR Fig. 6.1-1 13-B
SCEWS Ns. 13-B TER No. 42C i Date: 8/21/81 O EQUIPMD4T DR'IRONMENTAL QUALIFICATION SER/TER REVIEW J Millstone Unit 2 Docket No. 50-336 I j I) Summary of new information on SCEW sheet. None i II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O Facil r: Millstone Nuclear Pr. Sta. o o Unit: Two SYSTEM COMI-ONENT EVALUATION WORK SilEET Docket: 50-336 ENVIFONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METilOD ITEMS Parameter Spec. Qual Spec. Qual. 1800 CY 6 Operating In te rmi t- Sequential System: Aux. Feedwater 200 SY at Plant ID No.: Time tant 165 F, Note 1 3.e) Test ilV5276 1007 R.ll. Component: Valve Motor Temperature 2. Simultaneous
. Operators (OF) Profile 22 Profile 12 3, p, 3.d) Test Manufacture: Pressure Limitorque (PSIA) 11 Profile 12 2. Simultaneou:
A 3.d) Test Model Number: Operator S/N Palative 1., 2. Simultaneous 146658, 146659 tiumidity(s) 100 100 3 3.a) Test Function: Operators for FW-43A, FW-43B Chemical i NA NA NA l NA NA Spray Accuracy: Not Foguired Radiation g Sequential Service: 1 Aux. Feedwater NA 2.04x10 R NA 3.c) Test Isolatinn Location: Aging Plant Turbine Bldg. EL. Simulated Design Sequential 14'6" Zone T10 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev: Above Flood Level: Yes Sulunergence
- 3
- Documentation
References:
Notes: 1. Must be continually operated in a throttle
- 1. Bechtel Technical Spec. 7604-M-407 mode to control steam generator level.
- 2. FSAR Ammendment 17
- 3. Limitorque Test Report B0003 11/13/74 to 1/23/75
- 1) Par. 2.1.1 b) Par. 5.0 c) Par. 2.3 d) Fig. 1 e) Par. 2.1. 3 , 2. 2.1 11-1-80 14-B
-__~.
SCEWS No. 14-B TER No. 42D Date: 8/21/81 O EQUIPHENT ENVIRONMENTA1, QUA1.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None 4 II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
, (~
\ ) !
F ? . Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVlPD! STENT Note 1 DOCUMENTATIO:1 PIF* QUAL. OUTSTM4 DING METilOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Safety Inlection Operating N/A 76.5 Sec Fequenttal Plant ID No. Time Valve Must 'trake 4. 3.e) Test S1662, SI663 Stav as is ' lime Component: Valve Motor Temperature 2. Operators ( F) 111 F max. Profile 13 S imu l t a ne ou.< 3.c) Test Manufacture: Pressure (PSIA)
- I "" I #""U"'
Limitorque 11 Profile 13 Test 3 3.c) Model Number: Operator Relative 1*' 2* S/N 168874, 168875 Ilumidity (%) 100 100 Simultaneous Function: Operators for 3.d) Test S1662, SI663 Chemical Spray NA NA NA NA NA Accuracy: Not Required Service: Radiation Shutdown Heat Exchanger 3.33x10 6R 2x108R C,L Sequential to HPSI Suction 3.a) Test Incation: Aging Aux. Blde. EL (-) 45'6" Plant Sequential Zone A3(SI662) 40 Yrs. 40 Yrs. Design 3.b) Test Zone A2((SI663) ,' Life 1 Flood Level Elev: Above Flood Level: Yes Submergence nn
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-223B
- 2. FSAR Ammendment 17 1. These components must function in a radiation (only)
- 3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 envir nment.
a) Par. 2.1 b) Appendix C F-C3441 Par. 4.0 c) F-C 3441, Fig. 3 d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3
- 4. FSAR Fig. 6.1-1 11-1-80 15-B
SCEWS No. 15-B I TER No. A2E Date: 8/21/81 4 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of sulmittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Just ification for continued operation Not applicable O y/
_ ._ _- ~ .- _ _ _ ._ . .- - - - - . - _ . . - - ci" : Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET L i Docket: 50-336 } EQUIPMENT DESCRIPTION ENVIh0NMENT Note 2 DOCUMENTATION REFd QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. I Qual. N/A Intermit-
- System
- Safety Injection Operating Valve Must tant-30 mia, 6. 4.b) Sequential Plant ID No.: Time Stay as is Cycles for Test SI411, S1412 .9 Hrs.
Component: Valve Motor Temperature Operators (Op) i NA , Manufacture: Pressure Limitorque (pSIn) NA l Model Number: Operator l Ralative S/N 145934, 145933 Humidity (s) Function: Operators for NA SI411, S1412 Chemical Spray Accuracy: NA , Not Required Service: Radiation HPSI Pump Suction 5.13x10 5R 2.04x10 8 C 5. Sequential 3 Note 1. Test Incation: Aging Aux. Bldg. EL (-) Simulated Plant Segrential i 45'6" Zone A4 40 Yrs. 40 Yrs. Design 4.a) Test ! : Life Flood Level Elev: Above Flood Level: Yes Submergence . no
- Documentation
References:
Notes
- 1) Report 600376A applies to Radiation
- 1. Bechtel Technical Spec. 7604-M-223B Qualification Per Limitorque Telex
! 2. FSAR Ammendment 17 12/17/79
- 4. Limitorque Test Report 600198 1/2/69 to 4/29/69
- 2) Valves must function in a radiation (only) a) Page 5 envir nment.
b) Page 4
- 5. Limitorque Test Report 600376A 4/26/72 i.o 8/30/72 Par. 2.1
- 6. FSAR Fig. 6 1-1 11-1-80 16-B m_
SCEWS NJ. 16-B TER No. 42F Date: 8/21/81 O EQUIPMENT ENVIRONMDlTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Responss to SER concerns. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. ihe above referenced su veillance prograa will periodically verify the aging analysis. IV) Froposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program.
'.' ) Justification for continued operation.
Not applicable
w. O n v
, \
Facil : Millstone Huclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVII f ENT DOClb4ENTATIONREF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. 76.5 Sec. 3.e) Sequential System: Main Steam Operating Intermit- Stroke Test Time tant Time- Note 2 Plant ID No.: Hy4218 500 CY Component: Valve Motor Temperature 2. Operator FF) Profile 20 Profile 13 A, D Simultaneous 3.c) Test Manufacture: Pressure 2. 4 Limitorque (PSIA) Note 1 Profile 13 A Simultaneous 3.c) Test ' 1., 2. Model Number: Operator Relative S/N 156211 Humidity (s) 100 100 A simultaneous Function 3.d) Test Operator for MS- 65A ' chemical Spray NA NA NA NA NA Accuracy: Not Required Service: Steam Gen. No. 1 Radiation Sequential Main Steam Isolation NA 2.04x10 8R NA 3.a) Test Bypast; Incation: Encl. Bldg. Aging Plu: Sequential i EL 38'6" ' Jest Valve Rm. 40 Yrs. 40 Yrs. Design 3.b) Test Zone A50 , Lire Flood Level Elev: Above Flood Level: Yes . Submergence I nn 1 < i
- Documentation .teferences_: Notes:
- 1. Bechtel Technical Spec. 7604-M-223A l
- 1. The peak pressure er.vironment is 1.6 psig ,
- 2. FSAR Ammendment 17 -
- 3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 for a duration of about 13 seconds.
- 2. Used only during startup to warm turbine plant.
a) Par. 2.1 If it were open during a main steam line break b) Appendix C , F-C3440 Par. 4.0 , c) F-C 3441, Fig. 3 outside the containment it would receive a MSIS F-C 3441, Par. 3.2, Page 3-3 and must close and stay closed. d) e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 11-1-80 ' 17-B l
SCEWS Ns. 17-B TER No. 42G Date: 8/21/81 O. EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. () III) Response te TER concerns. FRC should review documentation which was obtained from limitorque as applicable to these valves at M111stene Unit 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable
,,.n,,,, . . , , , . . , , , , , _ , , . , , _ , _ , _ _ , , _ , ,, , _ _ _ , , . . _ _ _ , , , ___ ,, , , _ _ , _ , , _ , , _ _ _ , _ , _ _ _
a - - - . , _ _ . - , . -_ O O O Facil : Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SilEET Docket: 50-335 ENV1W t 1ENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ~ METilOD ITEMS Parameter Spec. Qual. Spec. Qual. 76.5 Sec. System: Main Steam Operating Intermit- Stroke Sequential Plant ID No.: HV4191 Time tant Time- Note 2 3.e) Test 500 CY Component: Valve Motor Temperature 2. ( F) Profile 20 Profile 13 A,D Simultaneous Operator 3.c) Test Pressure 2. Manufacture: (PSIA) Note 1 Profile 13 A Simultaneous Limitorque 3.c) Test Model Number: Operator Relative 1., 2. Humidity (%) 100 100 A Simultaneous S/N 155207 Function: 3.d) Test ! Operator for MS-201 ' Chemical i Spray NA NA NA NA NA
- Accuracy:
Not Required Sequential Service: Radiation 8 Steam Cen. No. 1 to NA 2.04x10 R NA 3.a) Test Aux. Feedwater Turbine ILeation: Encl. Bldg. Aging Sequential Plant i EL-38'6" West Valve Rm. Design Test Zone A50 40 Yrs. 40 Yrs. 3.b). Life ._ Flood Level Elev: ^ Above Flood Level: Yes Subnergence no 4
- Documentation
References:
Notes:
- 1. Bechtel Technical Spec. 7604-M-223A 1. The peak presssure environment is 1.6 psig
- 2. FSAR AMmendment 17 f r a duration of about 13 seconds.
- 3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 2. Must operate intermittently to supply steam a) Par. 2.1
- b) Appendix C, F-C3440 Par. 4.0 c) F-C 3441, Fig. 3 d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 18-B 11-1-80 i
SCEWS No. 18-B TER No. 42G ( Date: 8/21/81 , EQUIPMENT ENVIRONM GTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
, 1) Summary of new information on SCEW sheet.
None II) Resporse to SER concerns.(A) Refer to description of surveillance and preventive maintenance pregram contained in body of submittal. III) Respense to TEF concerns. FRC should review documentation which was obtained from limitorque as applicable to these valves at Millstone Unit 2. IV) Proposed corrective action and schedule. Equipme: . will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
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O O O Facil : Millstone Nuclear Pr. Sta. Unit: Two - SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVlkO MENT TX UMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION
~
~~
METi!OD ITEMS Parame+er Spec.
~
Qual. Spec. Qual. _ 76.5 Sec. System: Main Steam Operating Intermit- Stroke Sequential Plant ID No.: IIV4222 Time tant Time - Note 2 3.e) Test 500 CY Component: Valve Motor Temperature 2. Operator ('F) Profile 20 Profile 13 A, o Simultaneous 3.c) Test Pressure A. Manufacture: Limitorque (PSIA) Note 1 Profile 13 Simultaneous 3 3.c) Test Model Number: Operator Relative 1., 2. Humidity (%) 100 100 A Simultaneous S/N 156212 Function: 3.d) Test l Operator For MS-65B Chemical ; NA NA NA NA NA Spray i Accuracy: } Not Required i Service: Radiation Seluential l Steam Generator No. 2 NA 2.04x108R NA 3.a) Test Main Steam isolation 1 Incation: Bypass Aging i' Encl. Bldg. EL-38'6" Plant Sequential East Valve Rm. Zone A51 40 Yrs. 40 Yrs. Design 3.b) Test Life - Flood Level Elev: Above Flood Level: Yes Sulnergence un I
- Documentation
References:
_Not_e s : ,
. 1. Bechtel Technical Spec. 7604-M0223A 1. The peak pressure environment is 1.8 psig for i
- 2. FSAR Ammendment 17 " d
- 3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 2. se o y d dn a up o b M a p1 m .
a) Par. 2.1 If it were open during ' main steam line break b) Appendix C , F-C3440 Par. 4.0 outside the containment it would receive a MSIS a must c se a s ay el set d) .3 , r$ .2, Page 3-3 e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 19-B 11-1-80
i SCEWS No. 19-B i TER No. 42G Date: 8/21/81 O EQUIPMENT ENVIRONMETAL QUALIFICATION SER/TER REVIEW 4 Millstone Unit 2 Docket No. 50-336 I) Surrary of new inf ormation on SCEW sheet. None i II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. i III) Response te TER concerns. FRC should review documentation which was obtained f rom Limitorque as applicable to these valves at Millstone Unit 2. 4 i IV) Proposed corrective action and schedule. Equipment vill be incorporated into plant surveillance and preventive maintenance program.- V) Justification for continued operation. Not applicable . 1 I
O O O Faci' /s Millstone Nuclear Pr. Sta. SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION WVIRONMENT
~- METI!OD ITEMS Parameter ~ Spec. Qual. Spec. Qual.
~
76.5 Sec. System: Main Steam Operatin9 Intermit- Stroke Sequential Plant ID No.: IIV4189 Time tant T) m- Note 2 3.e) Test 500 CY Component: Valve Motor Temperature 2. Simultaneousi Operator ( F) Profile 21 Prof 11e 13 A, D Test 3.c) Manufacture: Pressure 2. Limitorque (PSIA) Note 1 Profile 13 A Simultaneous 3.c) Test Model Number: Operator Relative 1.,2. Simultaneous Ilumidity (%) 100 A Tc,t S/N 156208 100 Function: Operator 3.d) for MS-202 ~ Chemical Spray NA NA NA NA NA Accuracy: Not Required Radiation Sequential Service: Steam Cen. No.2 8 to Aux. Feedwater Turbine NA .2.04x10 R NA 3.a) Test [ t Iocation: Aging Plant ! Encl. Bldg. EL 38'6" Design Sequential East Valve Rm. Zone A51 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev: 1 Above Flood Level: les Subnergence un
- Documentation
References:
Notes: j
- 1. Bechtel Technical Spec. 7604-M-223A l 2. FSAR Ammendment 17 1. The peak pressure environment is 1.8 psig
- 3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 for a duration of about 13 seconds.
a) Par. 2.1 2. Must operate intermittently to supply steam to the aux. feed pump terry turbine, b) Appendix C, F-C3440 Par. 4.0 c) F-C 3441 Fig. 3 d) F-C '441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 11-1-80 20-B
1 SCEWS No. 20-B TER No. age Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket KO. 50-336
- 1) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TCR concerns. FRC should review documentation which was obtained from L imitorque as applicable to these valves at Millstone Unit 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O l l l
'N
<~ u) [Q Ftcil r: Millstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVlHONMENT Note 2 DOCUMENTATIO!I REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ~ METIIOD ITEMS Parameter _ Spec. Qual. Spec. Qual. Sequential Syste::.: Containment Spray Operating Continu- Continuous Note 1. 2.,4.a) Test Plant ID No.: P-43A, Time ous 5 dayn (Note 3.) P-43B Component: 4160V Temperatur n NA Pump Motor ( F) Manufacture: General Pressure tJA NA NA NA NA Electric Company (PSIA) Model Number: S/N Relative NA NA NA NA NA 8381499, 8381500 Numidity(s) Function: Develop Containment Chemical ; NA NA NA NA NA Spray Spray Accuracy: Not Required Service: Radiation Sequential Containment Spray 8.67x10 5R 1 x 106 R CL 2.,4.b),3. Test Location: Aux. Bldg. Aging EL-45'6" 40 yrs. 40 yrs. 1. 2.,4.c) Sequential Test Zone A2(MP43A) A3(MP43B) Flood Level Elev: Above Flood Level: Yes Suhnergence un
- Documentation Reference _s:
Notes: 1. FSAR Fig. 14.16-6. CS pumps are used to control
- 1. Bechtel Technical Spec. 7604-E-10, 7604-M-53. containment pressure. Containment pressure is at 0 psig
- 2. G.E. Ltr. O. A. Berquist to R.J. DeRosa, 9-22-80, after 10 sec.(ll.6 days).
- 3. NUSCO memo, R.J. DeRosa to file, GEE-80-746, 10-10-80. 2. Pumps are subject to radiation (only) environment.
'.. G.E. Topical Report, IEEE 323, Dec., 1978. 3. A load test for this qualification was not conducted. a) Section IV, Page 19 b) Section llI, Page 6 Qualification based on no load test of similar motor. c) Sumary Par. a), Page lii 21-B 11-1-80
SCEWS No. 21-B TER No. 43 Date: 8/21/81 O EQUIPMENT ENVIRONMDiTA1 QUAL.IFICATIOh SER/TER REVIEW Nillstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (T. H, QM-EXN) Containment spray purps are only required to operate for breaks inside containment-radiation is the only harsh environment. Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER centerns. FRC should review documentation which was provided by General Electric as applicable to the containment spray pump motors at Millstone Unit 2. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
Or O .o Facil : Millstone Nuclear Pr. Sta. Unit: Teo SYSTEM COMPONENT EVALUATION WORK SifEET Cocket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIROMMENT EQUIPMENT DESCRIPTION METHOD ITEMS l Parameter Spec. Qual. Spec. Qual.
~
Er'gr. Sateguard Continu- Continu-System: Room Air Recirc. Operating ous ous 1. 3.a) sequential Time test Plant ID No.. F-15% F-15B Component: 460V Fan Motor Temperature 2. (OF) 111 F peak 250 C A 3.b) sequential test , 7- - Manufacture: Pressure n li g H H Joy Mfg. Co. (PSIA) (Reliance Ee.ectric Co. Motor) 1., 2. Model Number:38-26.5-ll70 Relative 3.c) sequential ] SN-GF-157 47 Motor No. Ilumidity (%) 100 100 3 test Function:600277-14 Fan Drive Chemical ; NA NA NA NA NA Spray Accuracy: Not Fequired sependal 8
- Service: Engr. Sfgd. Room Radiation 8.60x106R 2.04x10 R test Air RecircuAation Fan C,L 3.d)
Incation: Aux. Bldg. Aging sequential ' 40 yrs, EL(-)45'6" Zone A2(Mt'15A) 0 yrs. at 174.8 c 1. 3.e) test , Zone A3(MF15B) Flood Level Elev: ! .Bove Flood Level: Yes Sutnergence nn
- Documentation
References:
Notes:
- 1. Bechtel Technical spec. 7604-M-507
- 2. FSAR 3.mmendment 17
- 3. Reliance Electric Co. Summary Report I NUC. 9, July 1, 1975 a) page 15 c) page 6 b) page 5 d) page 14 e) page 21 23-B 11-1-80
_. . . . . = _ . . _ _ _ _. _ . . _ .. 1 SCEWS No. 23-B TER No. 44 Date: 8/21/81 l i O v EQUIPMENT ENVIRONMDiTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 ! I) Summary of new information on SCEW sheet. i None f 1 II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. O SCEWS 23-B, reference 3 was provided by Joy Manufacturing Company as applicable to the ES Room Recirc. Fan at Millstone Unit 2. IV) Preposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive rainterance program. l. I V) Justification for continued operation. I I l Not applicable i l
O-Faci y: Millstone Nuclear Pr. Sta. O O Unit: Two H V .O:TM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EiWIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD EE Sheet 29(MP41A) 31(MP41B) 30(MP41C) Parameter Spec. Quai. Spec. Qual. _ , 180 Days-System: Safety Injection Operating Post Acc., 8320 hrs. Plant ID No.: P-41A, Time 100 Hrs /Yr. festing 3. 4. Analysis P-41B, P-410 Component: 4160V Temperature o 2' Safety Injection ( F) 110.5oF A 4., Note 1. Analysis Pump Motors Pressure Z. Manufacture: " Analy sis Siemens-Allis (PSIA) E 9 n 11 t medI 1 , 2. Model Number: riotor S/N Relative
., e . alysis 8-5112-90191-1-2, 8-5112- Humidity (%) A Function: 90191-1-3, 8- ]
5112-90191-1-1 Chemical i NA NA NA NA NA Pump Drive Spray Accuracy: Not Required Service: Radiation Sequential ! High Pressure 3.12x10 6R 2 x 10 8R C,L 4. Tests Safety Injection Iocation: EL- (-) 4 5 ' 6" Aging 40 yrs. l- 5 Analysis Zone A2(MP41 A) A4(MP418) 40 yrs A5(MP41C) Flood Level Elev: Above Flood Level: Yes Sutruergence nn
- Documentation
References:
Notes: 1. The autors were designed for an ambient of
- 1. Bechtel Technical Spec. 7604-M-761 only 0.5 F less than the spec. requirement. This (Combustion Engineering Spec. No. 18767-PE-410) difference is insignificant especially since the avail-
- 2. FSAR Ammendaent 17 able data indicates the operating temp. rise is well
- 3. NUSCO memo, K.M. Kacich to R. DeRosa, below rated.
NEE-80-L-350 dated 8-7-80. .
- 2. Insulation is class B, non-hygroscopic.
- 4. Siemen's-Allis inter-office correspondence 3. Motor surveillance intensified in Plant Perventive dated October 8, 1980.(revised October 16, 1980) Maintenance Program.
- 5. Wyle Report 17436-2, Rev. A dated 2-27-81 25-B 8-21-81
SCEWS No. 25-9 l TER No. 45 Date: 8/21/81 n C:) EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER R* VIEW Millstone Unit 2 i Docket No. 50-336 I) Summary of new information on SCEW sheet. Aging analysis utilizing Arrhenius Methodology connletes qualification. II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program concr*.ned in body of submittal. III) kesponse to TER concerns. O' FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance End preventive maintenance program. V) Justification for continued operation. Not applicable i t i
l O Facil 1: Millstone Nuclear Pr. Sta. O O ' S'!ATEM COMPONENT EVALUATION WORK SilEET Unit. Two Docket: 50-336 e ENVIRONMENT DOCUMENTATIOi, REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION
,EE Sheet 32(MP42A) METHOD ITEMS 33(MP42B) Parameter Spec. Qual. ~ Spec. Qual. 3y 6 Hrs. Post' $$
System: Safety Injection Operating [j *li r. 40,006 hrs Plant ID No.. P-42A, Time Testing Note 2. 3. Analysis 2 '" n1 4 P-42B _ < o Component: 4160y Temperature 2. $o ( F) 111 F max. 110. 5F A 3., Note 1. Analysis '.'" Safety injection Pump Motors Pressure 2. 5{ x< Manufacture: Siemens-Allis (PSIA) 0.5 psig h
^
H Analysis { EU oa Model Number: Motor S/N Relative 1., 2. Analysis 8-5717-90191-2-2, 8-5117- Humidity (%) 100 100 3 3., Note 3. m ,, o Function: 90191-2-1 .e n a-Chemical o .2 Pump Drive Er
.' pray NA NA NA NA NA Accuracy: ,$ h Not Required s us ! Service: Low Pressure Radiation Sequential
- Safety injection 4,1x10 6R 2 x 108 R C,L 3. Test h
_ _ c. Location: Aux. Bldg. Aging 40 yrs. 40 yrs. 4 Analysis E 1* Note 4* EL.(-)45'6" Zone A2(MP42A) A3(MP42B) Flood Level Elev: Above Flood Level: Yes Subnergence un i
- Documentation
References:
Notes: 1. The motors were designed for an ambient of only
- 1. Bechtel Technical Spec. 7604-M-762 0.58 F less than the spec. requirement. Th!s difference is
. (Combustion Engineering Spec. No. 18767-PE-410) insignificant especially since the available data indicates
- 2. FSAR Ammendt:ent 17 the operating temp. rise is well below rated.
, 3. Sieman's-Allis inter-office correspondence 2. FSAR Sec. 6.2.3.1. Sump recire. can start as early as 44 dated October 8, 1980. (revised October 16, 1980) ninutes into an accident for a large break. 6 Hrs. is
- 4. '4yle Report 17436-2, Rev. A dated 2-27-81 et -.imated for smaller breaks. Pumps will not be subjected to a harsh environment until plant goes into recire.
- 3. Insulation is class B, non-hygroscopic.
26-B G-21-81
)
~.
SCEWS No. 26_n TER No. 4s Date: 8/21/81 EQUIPMENT ENVIRONMENTAL. QUALIFICATION SER/TER PEVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. < Aging analysis utilizing Arrhenius Methodology completes qualification. II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. () III) Response to TER concerns. FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. I Not applicable O
n istone Nuclear Pr. Sta. {t rac211( ) [ ] ATION UORK SHEET SYSTEM COMPONENT bv
\
Unit: Two Docket: 50 6 DOCUMENTAT I REF* QUAL. OUTSTANDING ENVIPONMDIT 1:QUIPftENT DF.SCRIPTION - "~~ MET!!OD ITEMS Parameter Spec. Qual. Spec. Qual. Contin- Sequential System: Operating Contin- uously Test Plant ID No.. MPllA, Time uously 5 days Note 2. 3. ,4. a) (Note 1.) MPllB, MPllC Component: RBCCW Temperature A,2 BY DESICF' Pump Motors (Or) 110"F max. 1400F 3. 5. Manufacture: Pressure General Electric Co. (PSIA) It H A,2 11 11 Model Number: SK818847A129 Relative 3.,5. TEST OF 100 100 1. S/N's LG8381496,7,8 flumidity ( %) SIMILAR DFSTCN Function: PBCCW Pump Drives Chemical ' Spray NA NA NA NA NA Accuracy: Not Required Service: 4000V Radiation NA NA NA NA NA Location: Aux. Bldg. ^9 in9 Sequential El. (-)25' 6" 40 yrs. 40 yrs. 1. 3.,4.b) Test Zone AlB Flood Level Elev: Above Flood Level: Yes Subnergence nn Notes: 1. A load test for this qualification was not
- Documentation
References:
- 1. Bechtel Spec. 7604-E-10, 7604-M-41A. conducted. Qualification is based on no load test of similar motor.
- 2. FSAR Amendment 17. 2. Must operate continuously until maintenance can be per-i 3. G.E. Ltr. 0.A. Berquist to R.J. DeRosa, dated formed on alternate pumps to supply cooling water to Oct. 10, 1980 on RBCCW pump motors.
- 4. G.E. Topical Report,IEEE 323 Dec safety related components.
a) Section IV. Page - 19 b) $umma r. , 1978y Par. a), Page lii
- 5. G.E. Ltr. 0.A. Berquist to R.J. DeRosa on containment spray pu'p motors, Nov. 15, 1979 29-B 3-21-81
eco , .. ,u_. TER No. 46 Dats: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATI0!! SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. Reference 4 describes the rest of a similar motor insulation system to that in SCEWS 29-B. The motor successfully operated for 5 days after standing in 100% humidity for 168 hours. II) Response to SER concerns.(QM, QT, T H. A.) Reference 5 adacuately addresses temperature. Reference 3 documents the applicability of reference 4. Refer to description of surveillance and preventive maintenance program contained in body of sabmittal. s III) Respense to TER concerns. fg FRC should review documentation which was provided by General Electric as
\.,,/ applicable to the Millstone Unit Two RBCCW Pump Motors.
IV) Propoced corrective actien and schedule. Equipnent will be incorporated into plant surveillance and preventive maintenance progran. V) Justification for continued operation. Not applicable a V
ras.242 Unit:
'Istone Nuclear Pr. Sta.
SYSTEM COMPONE.- ATION WORK SHEET ( ), Docket: 50-336 ENVIPONI ENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METilOD ITEMS Parameter Spec.- . . . Qual. Spec. Qual. Operating B2 design see System: Electrical Cop t.J :aucu s Continuous 1 Plant ID No.. B52 Time Qualification Box Component: Motor Control Temperature 239 for 56 3.d) Profile 24 days - 131 2 . , A . ,F,. 3.a) Simul tancot s Center ( F) for 96 hrs Note 1 Test Manufacture: Pressure
^ '
General Electric Co. See Model Number: Relative Simultaneous summary ilumidity (s) 100 99 1 3 a) Test shee t-Function: Supplies power to Cat. 1 Electrical Chemical Loads Spray NA NA NA NA NA Accuracy: Not Required Service: 4E UV Radlation NA NA NA NA NP. Location: Aux. Bldg. Aging Pl ant El. 36' 6" 40 yrs. 40 yrs design 3 b) Sequential life test Zone A49 Flood Level Elev: Above Flood Level: Yes Sutnergence nn
- Documentation
References:
Notes: U The temperature excursion above the test profile is of short 1 Bechtel Spec. 7604-E-7 durat'lon. Based on engineering judgement, NNECO concludes
- 2. FSAR Amendment 17 that this equipment would satisfactorily perform its safety
- 3. Wyle Laboratori'ss NEQ Test Report 4357-2, function.
September 27, 1978 a) page X-1 b) page III-l d) page VII-l 30B 11-1-80
SCEWS No. 10 8 TER No. 48 Date: 8/21/81 A V EQUIPMENT ENVIRONMENTAL. QUALIFICATION , SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (H. QI, A) This equipment is to be encapsulated to orevent steam entry fato MCC. III) Response to TER concerns. FRC should review documentation. t l IV) Propcsed corrective action and schedule. Refer te corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. l l 1 I i I
SUM 4ARY SHEET NO. SCEW SHEET NO. 30B
- REV. 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUltlARY MILLSTONE UNIT 2 MOTOR CONTROL CENTERS B52 EQUIPMENT:
MANUFACTURER: General Electric QUALIFICATION DISCREPANCY: Subject equipment lacks sufficient qualification documentation with respect to humidity. SAFETY FUNCTION AND JUSTIFICATION
- FOR CONTINUED OPERATION:
The subject motor control centers provide 480V AC power to motor operated valves which operate to mitigate the consequences of a main steam line break outside of the pri::ary containment. The MCC will have performed and completed its safety function within 60 seconds *after the start of an accident. Based upon engineering judgement, NNECO concludes that the MCC would satisfactorily perform its safecy function since the environmental conditions within the MCC enclosures would not be as severe as the profiles identified for ambient conditions and thus would not prevent the performance of this equipment during the time for
~* which its correct cperation is credited. Due to the desirability of long term operability of this equipment each MCC will be encapsulated such to preclude the humid environment. This will be accomplished as soon as practicable prior to June 30, 1982 assuming that procurement delays do not preclude protection by that date.
l *Except to.- aux feed valves. The motor operators for these valves will be l replaced with air operators during the next refueling outage which is scheduled to commence in December 1981. This will make the auxiliary feed system AC power independent as indicated in the W. G. Counsil to R. A. Clark letter dated February 19, 1981. l
'O o
e
n Q
\) (n)m, C# .uo.44 U: 'lat one fluclear I r. Sta ,
ATION WORK SHEET Unit: Two SYSTE!! COMPOMENT Et Docket: 50-336 ENVIRONMEM DOCUMt N ATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. see system: Electrical Operating Continuous Continuous 1 By design Qualification Plant ID No.: B51, B61 Time box Component: Motor Control Temperature 131 for Centers (OF) ll2'F max. 96 hours A., 2 3 a) Simultaneous Test Manufacture: Pressure (PSIA) H 11 A.. 2 11 1[ General Electric Co. see Model Number: Relative Simultaneous summary Humidity (t) 100 99 1 3 a) test Function: Supplies power sheet to Cat. 1 Electrical Chemical Loads Spray NA NA NA NA NA Accuracy: Not Required Service: 480V Radiation NA NA NA NA NA J Incation: Aux. Bldg. Aging 40 yrs 40 yrs n 3 b) Sequential El. 14' 6" life test Zone A24 Flood Level Elev: Above Flood Level: Yes Submergence . - nn
- Documentation
References:
Notes:
- 1. Bechtel Sgc. 7604-E-7
- 2. FSAR Amendment 17
- 3. Wyle Laboratories NEQ Test Report 43757-2, September 27, 1978 '
a) Page X-1 b) Page III-l 31B 11-1-80
l SCEWS Na. 31B TER No. 48 Date: 8/21/81 EQUTPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 l I) Summary of new information on SCEW sheet. None II) R< sponse to SER concerns. (H. QI. A.) This equipment is to be encapsulated to prevent steam entry into MCC. III) Response to TER concerns. iRC should review documentation, f)4 u IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Ref er to corresponding equipment summary sheet. O
1 StBenRT SEEET N0. ; i 31B . SCIW SEEET NO.
?q y -
EQUIFMENT ENVIRONMENTAL QUALIFICATION i DISCREPANT EQUIPMENT StBGERY MILLSTONE UNIT 2 MOTOR CONTROL CENTERS B51, B61 EQUIPMENT: General Electric MANUFACTURER: QUALIFICATION DISCREPANCY: Subject equipment lacks sufficient qualification documentation with respect to humidity. (
/ SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
The subject motor control centers provide 480V AC power to motor operated valves which operate to mitigate the consequences of a main steam line break outside of the primary containment. The MCC will have performed and completed its safety function *;it'nin 60 seconds after the start of an accident. Base d upon ensinaerir.g judgement, NNECO concludes that the MCC would satisfactorily perform its ssfety functior. since the environmental conditions within the MCC enclosures wculd not be as severe as the profiles identified for ambient conditions and thus would not prevent the performance of this equipment during the time for which its correct operation is creditec Due to the desirability of long term operability of this equipment each MCC will be encapsulated such to preclude the humid environment. This will be accomplished as soon as practicable prior to June 30, 1982 assuming that procurement delays do not preclude protection by that date. . 8 O
O O O Facility: m listone Nuclear Pr. Sta. Unit: Two SYSTE" COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONME DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION '- MET 110D ITEFS Parameter Spec. Qual. Spec. Qual. Simul ta-System: Main Steam Operating neous Plant ID No.- PV 4223, Time P Continuous P 1.a) Test PV4224 Simulta-Component: Solenoid Temperature o Valve ( F) 324 F Profile Profile neous 10 20, A 1.b) Test Manufacture: ASCO Pressure Simuita-(PSIA) 1.6 psig Profile A 1.b) neous . 10 Test Simulta- ; Model Number: Relative
^ '
NP-206-381-6F liumidity(%) 100 1.c) neous Test Function: ~ Pilot Valve Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test Service: Continuous Radiation Sequential
#16 #2 Atmospheric Dumps N/A 2x 10 8R N/A 1.e) Test Incation: Aux. Bldg. Aging Req. maint.
EL. 36'6" Sequential performed Zone A50(PV4223) Test every 3 yrs A51(PV4224) 40 Years 4.4 Years PDL 1 Flood Level Elev: Above Flood Level: Yes Subnergence un
- Documentation
References:
~
Notes:
- 1. ASCO Test Repart No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 35-B 11-1-80
SCEWS No. 35-3 49 TER No. Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW she + None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of subt!.ttal. III) Response to TER concerns. Sare as II. IV) /roposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
-- . - , . , _ . . , - - , - - _ _ _ . , _ _ . , _ . ,, ,,,._,,,., _,,,.,., _.,.,-, -. , ...c_. . . ~ - , _ - . _ , . _ . , , _ , _ _ . . -
O O O Facility: .11 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION EINIRCNMENT DOCUMENTATION REF* QUAL. OUTSTANDING METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. Continuous See summary System: Main Steam Operating Plant ID No.: Time sheet 36Ba PT 4223, Component: Temperature See summary Pressure transmitter (OF) 324 F 185"F Profile I sheet 21, A 36B Manufacture: GE/MAC pressure See summary (PSIA) 1.6 psig A sheet 36B Model Number: 551 Relative See summary Humidity (%) 100% 100% A 2 sheet 3on Function: Initiating sig- i nal for steam generator Chemical atmospheric dump Spray Accuracy: N/A Service: Steam Radiation Generator Pressure . N/A
- Locat: ion : Aux. Bldg. Aging See summary EL. 36'6" Zone A50 40 Years P.D.L. sheet 36B Flood Level Elev:
Above Flood Level: Yes Submergence nn
- Documentation
References:
Notes:
- 1. CE instruction 198-45 32 K11-001A
- t. 2. Not af fected by exposure to MIL-E-52.'2 x humidity test (24 hr. cycle, 680F to
- 1500F at 100% relative humidity).
]l-1-80 36-B
SCEWS No. 36-B i TER No. 50 Date: 8/21/81 j' (A f EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns (RPN,T,R, A. QM,) This equipment will be replaced with fully qualified devices III) Response to TER concerns. Same as !!.
- 'i) Proposed corrective action and schedule.
Refer to corresoonding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipme.it summary sheet. O l l
k. i O- O , O
) Facility: .llstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMF.HT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD > ITEMS Parameter Spec. Qual. Spec. Qual. _ ,
- System
- '4ain Steam Operating Continuous See summary Time sheet Plant ID No.: PT-4224 4 36B Component: Temperature 326 F Profile hee B Pressure transmitter 185"F 20, A 1 j Pressure bee aummary Manufacture: GE/MAC sheet 36Ba (PSIA) 1 .8 peig A g
See summary , Model Number: 551 Relative Humidity (%) 100% 100% A 2 sheet 36Ba . 4 ' 1 Function: Initiating sig- ! nal for steam generator ' Chemical , atmospheric dump SprayN /A i Accuracy: ' . 4 j Service: S t ea.a Radiation , Generator pressure
- N/A Incation: Aux. Bldg. Aging See summary Elev. 36' 6" 40 Years P.D.L. sheet 36Ba >
- Zone ASI i t " Flood Level Elev: , Above Flood Level: Yes Submergence un
*Douunentation
References:
Notes: *
- 1. GE instruction 198-4532KIL-0011
- 2. Not affected by exposure to MIL-E-5272 i humidity test (24 hr. cycle, 68 F to 150 F I I
4 at 100% relative humidity). , s 1 1 36-Ba 11-1-80
SCEWS No. 36-Ba TER No. so Date: 8/21/81 O's EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket 15. 50-336 I) Summary of new inf ormation on SCEW sheet. None II) Response to SER concerns. (RPN, T, R. A QM) This equipment will be replaced with fully qualified devices. III) Response to TER concerns.
/T Same as II. %)
l 1 1 i I'l) Proposed corrective action and schedule. Refer to corresponding equdpment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. l 5
36B, 36B SIRetARY SHEET NO. 36B, 36Ba SCEW SHEET NO.
*Date: 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDMARY MILLSTONE UNIT 2 STEAM GENERATOR PRESSURE TRANSMITTERS BQUIPMENT:
PT-4223, 4224 MANUFACTURER: GENERAL ELECTRIC MEASUREMENT AND CONTROLS (CE/MAC) This equipment is discrepant because it lacks QUALIFICATION DISCREPANCY: documented qualification test data. I SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: These components provida control loop input for automatic operation of the atmospheric dump salves. This subject was also discussed in the October 5, 1979 letter from W. G. Counsil to H. R. Denten. To date the s'taff has not responded negatively to this letter, thereby inferring concurrence with the conclusions presented therein. With the postulation of the most adverse failure of these cow onents there is no effect upon the control room manual operation of the atmcspheric dump. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. O
+- _ _ _ . _ ,
O O O d V Facility: . llstone Nuclear Pr. Sta. Unit: 'Ivo TSTIM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESC,dPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Main Steam Operating Continuous See summary Plant ID No.: Various Time sheet 40B, 40BA Component: Temperature See ( F) 3240F Profile summary sht solenoid operated valver 21, A 40B, 40BA 5"" Manufacture: ASCO Pressure (PSIA) summary sht 1.6 psig A 40B, 40BA Model Number: Relative See HPX8211B54SW HumiJiry(%) 100g simmary sht A 40B, 40BA Punction: bee Pilot solenoid valve Chemical Spray summary sht Accuracy: NA N/A 40B, 40BA i See Service: Main steam Radiation isolaticn trip valve N/A summary sht pilot operator 40B, 40BA Location: Aux. Bldg. Aging See EL. 36'6" 40 Years P.D.L. summary sht Zone A50 40B, 40BA Flood Level Elev: Above Flood Level: Ves Subnergence nn
- Documentation Referencq1: Notes:
HY-4217 Al HY-4217 B1 HY-4221 Al HY-4221 B1 40-B 11-1-80
SCEWS N2. an_n TER* . si Di' 8/21/81 i O EQUITMDiT ENVIRONMENTAL QUALIF~ IION SER/TER REVIEW Millstone Unit
- Docket No. 50-1 ,o I) Summary of new information on SCEW sheet.
None II) Resronse to SER concerns. (RPS, T, P, R, QM, QI, A) This equipment will be replaced with fully qualified devices. , ( III) Response to TER concerns. 1 Same as II. IV) Proposed corrective ac.;;n and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. l O
i\ s L] \ . Facility: .llstone Nuclear Pr. Sta. Unit: Two SYRf f*4 COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. See System: Main Steam Operating Continuous summary sht Plant ID No.: Various Time 408 C%ponent: Solenoid Temperature See Profile operated valves (oF) 326 F 20, A 40B, see Manufacture: ASCO Pressure s (PSIA) 1.8 psig A 40 Model Number: Relative 100% Humidity (%) summary sht IIT-8211D4 A 40B, i Function: Pilot See solenoid valve ' Chemical Spray summary sht 40B, 4 Accuracy: N/A N/A See Service: Main steam Radiation summary sht isolation trip valve N/A 40B, pilot operator _ Aging See Incation: Aux. Bldg. 40 Years P.D.L. summary sht El. 36' 6" 40B, Zone A51 Flood Level Elev: Above Flood Level: Yes Submergence
- nn
- Documentation
References:
Notes: ilY-4217 A2 liY-4217 B2 liY-4221 A2 HY-4221 32 40-Ba 11-1-80
o %- @ ( ) 9 /g #4 hp, g%f/ V &p og,Ay,( s%a
; Vg@4
,s ,s NV" IMAGE EVALUATION 4,,,Nd*
N TEST TARGET (MT-3) l'O W Eld HM I
-2 iSIE !l=25
=
l-l 5 EM l u
.8 1.25 I l.4 1.6
- == 1__
< 6" >
N ,' ffz# 'S)k,h
' '4
- k. __
TEST TARGET (MT-3) 1.0 's Ela BM l9 mM a Bu
==
l,l h,
- bN ll!-!8 I.25 1.6
]i.4 - s.. .
5% '
++b ,,,D/ ' o,. .
k 4 l,
#*f)$>4%$*'+#, eEEv <e 1,.
TEST TARGET (MT-3) i 1.0 58EHM
.S
_ uam yp=2 = l,l p bb Lh! 1.4 i.6 l.25 l l
- 6, ,
4
#4 b ?%<$4 44l7gi 7/ ..
+,,+.&
;*9,s.
SCEWS No. 40Ba TER No. s? Date: 8/21/81 O EQUIPMENT ENVIRONMDiTAL QUA1.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 l I) Summary of new inr ormation on SCEW sheet. l l None II) Response to SER concerns. (RPS, T, P, R, QM,QI, A) ! This equipment will be replaced with fully qualified devices. I III) Response to TEF concerns. Same as II. 1 IV) FT: posed corrective action and schedule. Refer to corresponding equipment summary 'heet. v) Justification for continued operation. Refer to corresponding equipment summary sheet. O
st39EART SEEET NO. 40B, 40BA SCEW SHEET MO. 40B, 40BA D) (_f DATE: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUtelARY MILLSTONE UNIT 2 Solenoid Operated Valves EQUIPMENT: Main Steam Isolation Valve Pilot Operators Automatic Switch Company (ASCO) MANUFACTURER: These compor. cats are discrepant because they
- QUALIFICATION DISCREPANCY: lack doc'imented qualification test data.
( SAFETY FUNCTION AND .7USTIFICATION \ FOR CONTINUED OPERATION: These equipments function as pilot operating devices for the main stesm isolation valves, (MSIV). The engineered safety features actuation response time for main steam isolation is 6.9 secotds as specified in the technical specifications. The reoundant solenoid valves on each MISV which isolate the air supply to the MSIV de-energize on an isolation signal to accomplish this function within the first second of the accident. The solenoid valves required to operate to vent the MSIV operator must energize to vent. Reasonable assurance is provided for performance of this function as described by the existence of the following conditions: Each MSIV is provided with two separate and redundant vent SOV's. These SOV's will open (energize) within the first second of the accident initiation. The coils of these components are rated for continuous energization with maximum fluid temperatures existing within the SOV. These components are de-energized and at ambient temperature at the onset of the accident. Given the mass of the components, their initial de-energized state and the high temperature rating of the coil assemblies, it is extremely unlikely that these components would experience an environment which exceeds their rating and results in their failure prior to their performing their function within the required time. rx L)
r:g2 4 SAFETY FUNCTION AND JUSTIFICATION
SUMMARY
SHEET NO. 10B, 40BA FOR CONTINUED OPERATION: SCEW SHEET NO. 40B, 40BA Date: 8-21-81
~
(' ~')
' The MISV's are reverse acting check valves. Hence when a MSIV closure is initiated differential pressure across the MSIV assists in closure of the valve, therefore, reducing the actual closure time to considerably less than the 6.9 seconds identified as required by the technical specifications.
This matter was also discussed in the October 5, 1979 letter from W. G. Counsil to H. R. Denton. To date the staff has not responded negatively to this letter, thereby inferring concurrence with the conclusions presented therein. The manufacturer is currently a.alyzing these components with respect to the accident environment experienced, to establish an operable life for these components under accident conditions. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. N / m
!3 (3 V (V3 \_/
Facility: .411 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK S!!EET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF' QUr.L . OUTSTANDING EQUIPMENT DESCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. I Safety Injection Simulta-System: r, Ctmt. Spray Operating g Plant ID No.- Time 1.a) P Contiunous P Test HY-306 Simulta-Component: Temperature ( F) 111 F Profile 3 1.b) neous Solenoid valve 10 Test $ Manufacture: ASCO Pressure Simulta-(PSIA) 0.5 psig Profile A , il 1.b) neous ] 10 Test Model Number: Relative Simulta-
^ 1.c) neous NP-8320A177E Ilumidity(%) 100% 100 est Function: Pilot solenoid valve Chemical Simulta-Spray neous l Accuracy: NA N/A B N/A 1.d) Test Service: Control shutdown Radiation Sequential cooling flow Bypass 2.294 n6, 2 x 108 R C, L 1.e) Test Location: Aux. Bldg. Agin9 Req. maint. ! EL. (-) 45'6" Sequential performed LPSI Pump Room Zone A-2 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:
Above Flood Level: Yes Subnergence un ]
- Documentation
References:
Notes: This component subject to radiation (only)
- 1. ASCO Test Report No. AQS 21678/TR Rev. B environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 43-B 8-21-81 e
SCEWS Ns. 43-B TER No. 53 Date: 8/21/81 O' EQUIPMENT ENVIRONMDITAL QUAL.IFICATION SER/TER REVIEW Milletone Unit 2 Docket No. 50-336 I) SumLary of new information on SCEW sheet. Radiation level specified revised. II) Response to SER concerns. (A) Refer to descr . ion of surveillance and preventive maintenance program centained in body of submittal. III) Response to TER concerns. Same as 11. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operatic.. Not applicable
- O
O O .. O Facility: ..illstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET DotAet: 50-336 i ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METi!OD ITEMS 4 Parameter Spec. Qual. Sper. Qual. Simulta-System: Feedwater Operatin9 neous 4 Plant ID No.- Tim HY-5419, P Continuous P 1.a) Test Component: 5421 Temperature 324 F S mt Ita-pgg Solenoid valve 10 21, A 1.b) Test 1 snufacture: ASCO Pressure S*multa-(PSIA) 1.6 psig Profile Note 1 1.b) neous 10 Test Model Nu'nber: Relative * #~ 100% A NP-8320A183E Ilumidity (%) 100 1.c) ncous Ebnction: Test Pilot > lenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test 4 Service: Continuous Radiation Sequential N/A 2 x 10 8 R N/A 1.e) Test Location: Aux. Bldg. Aging Rcq. maint. EL. 36'6" Sequential performed Zone A-50 40 Years 4.4 Years PDL 1 Test evecy 3 yrs Flood Ievel Elev: Aoove Flood Level: Yes Subnergeme un
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS '1678/TR Rev. B 1. The environmental pressure is less than 2 PSIG a) Appendix A Par. 5 b) Appendix A Fig. 9.2 for a duration of about 13 seconds. This is I c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 considered insignificant, e) Appendix D 46-B 11-1-80 i
SCEWS ND. 46-B TER No. u Date: 8/21/81 I O EQUIPMENT UVIRONMENTAL QUA1.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Respor se to SER concerns. (A) Refer to description of surveillance and preventive maintenance prograw centained in body of submittal. III) Response to TER concerns. O Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicrble a O n.,-,<,,-.-.--~ ~ - - - - - ~ - . - - . - , . - - - - - - -
O O O Facility: listone Nuclear Pr. Sta-Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 m ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION l'ETIIOD ITEMS Parameter Spec. Qual. Spec. Qual.
"" ^^
System: Feedwater Operating Plant ID No.: IIY-54 2 0, Time P Contimious I 1.a) e Component: Solenoid Temperature Simulta-Valve ( F) 326 F Profile Profile neous 10 20, A 1.b) Test Manufacture: ASCO Pressure Simulta-e 1 neous 10 1.b) Test Model Number: Relative 100% 100 A 1.c) Simulta-NP-8320A183E Humidity (%) neous Function: Test Pilot solenoid valve ~ Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Continuous Radiation Sequential N/A 2 x 10 8 R N/A 1.e) Test Incation: Aux. Bldg. Aging Req. maint. El. 36' 6" Sequential performed Zone A-51 ' 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Subnergence nn
- Documentation Keferences: Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B 1. The environmental pressure is less than a) Appendix A Par. 5 b) Appendix A Fig. 9.2 2 PSIC for about 13 seconds. This is c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4. 2.4. 3 considered insignificant.
e) Appendix D h 11-1-80
SCEWS No. 46-Ba , TER No. 54 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None
! II) Response to SER :oncerns. (A)
Refer to description of surveillance and preventive maintenance program contained in bo+y of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective r.ction and schedule. Egi:1pment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
V) fi V w Facility: n.11 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DF.SCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING MET!!OD ITEMS Paramet ~ Spec. Qual. Spec. Qual. _ Safety Injection Simulta-System: & Ctmt. Spray Operating neous Plant ID No.: Time P Continuous P 1.a) Test 11Y-657 Component : Temgwer..ture Simulta-( F) A Solenoid Valve 111 p Profile neous 10 1.b Test Manufacture: ASCO Pressur 0.5 psig Simulta-A, II (PSIA) Profile neous 10 1.b) Test Model Number: Relative Simulta-Ilumidity (%) ^ neous NP-8320A177E 100 1.c) Punction: Pilot solenoid Test valve Chemical Simulta-Spray neous Accuracy: NA NA B NA 1.d) Test Service: Continuous Radiation Sequential 8 2.38x10 bR 2 x 10 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint. EL. (-)45'6" Sequential performed LPSI Pump Room Zone A-2 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Suhnergence nn
- Documentation
References:
Notes: This component subject to radiation (only)
- 1. ASCO Test Report No. AQS 21678/TR Rev. B environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 47-B 11-1-80
SCEWS Na. 47-B TER No. 53 Date: 8/21/81 / 'N
~/
EQUIPMENT DWIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Su==ary of new inf ormation on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable (~
%_ j
0 v f s e U Ffcility: I acton2 Nuclear Pr. Sto. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 i i DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT MEntOD ITEMS Parameter Spec. Qual. Spec. Qual. Salety Injection System:6 CTNT Spray Operating g,, , ,,
- Plant ID No.
- Time note 1. note 1. note 1. note 1. note 1. Sheet 47-Ba ZS-657 Component: Limit Seitch Temperature
( F) see sumary 1080F 1 sheet 47-Ba Manufacture: NAMCO Pressure i see summary 0.5 psig 1 sheet 47-Ba Model Number: Relative see sumary FA170-31100 Humidity (t) 100% A sheet 47-Ba Function: Shutdown Hx. bypass to MN LPSI hdr. Chemical Spray Accuracy: N/A N/A Service: Shutdown cooling Radiation see sumary flow control valve sheet 47-Ba 2.29 x 10 6R C,L _ l Incation: Aux. bldg. Agin9 plant e le . (-)4 5 ' 6" design see sumary j fire zone A-2 40 yrs. life sheet 47-ft Flood Level Elev: Above Flood Imvel: Yes Sulmergence 1 Notes ', )
- Documentation References?
1 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. Not applicable. Valve is administratively controlled. FSAR Figure 9.3-1 (Locked Closed). I 2. This component subject to radiation (only) environment. i 4 i 47-Ba 1/30/81
- 1 StgelARY SEIET NO. 47-Ba ;
SCEW SHEET NO. 47-Ba
, 8-21-81 EQUIPMENT ENVIROISENTAL QUALIFICATI0H DISCREPANT EQUIFtGNT SUtelARY CONNECTICUT YANEEE EQUIPMENT: Stem Mounted Limit Swite' ZS-657 Shutdown Cooling Flow Control Valve MANUFACTURER: National Acme Corporation (NAMCW QUALIFICATION DISCREPANCY: This componet t lacka documented qualification data. !
t FUt;CTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: This equipment provides contacts for ( control circuit input and position indication for shutdown cooling flow control valve. They are all loct .ed outside the containment and are subject to an environment which is enveloped by the equipment catalog specification, therefore, the environment will not impair these components in performance of their attended function. This equipment is required to function af ter a design basis event to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of " indication only" devices. l t O
A %) Q#l Facility listone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EhmUATION WORK SilEET j Docket: 50-336 EfNIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MET!!OD ITEMS Parameter Spec. Qual. Spec. Qual. System: S/G Blowdown Operatin9 Sequen t ia l Plant ID No.: Time Continuous Continuous P 1 Test ZS-4246, 4248 Component: Limit switch Temperature Sin.olta-FF) ll20F A ne us Profile 7 1.a) Test Manufacture: NAMCO Pressure Simulta-(PSIA) neous 0.6 psig Profile 7 A. II 1.a) Test Model Number: Relative Simulta-EA740-20100 Humidity (s) ne us 100% A 100 1.b) Test Function: Position Indication & Valve Chemical Simulta- 'l Spray - neous Control pfg Accuracy: NA Note 2 NA 1.c) Test Service: S/G Blowdown Radiation C Sequential isolation valv 8 AldO R 5 2.04x10 8R 1.b) Test Incation: Aging 40 yrs. Test Casket repla cement Aux. Bldg. 40 yrs. except P.D.L. 2 Analytis requfred El. (-) 5' 0" Zone A17 gr1ket ever 2 yrs. (7 yve 1 Flood Level Elev: Above Flood Level: Yes Submergence un
- Documentation
References:
Notes: 1.This component is subject to a radiation (only)
- 1. Vendor qual. report, plant file MRIR #1-26-79 environment.
; a) Fig. 1, Page 11 of 12 b) Page 4 of 12 2. The spray was composed of boric ecid, water, sodium c) Pa;;e 8 of 12 thiosulfate, and sodium hydrodde, Pli between
- 2. Wyle Report 17436-3 10 & 11 (3000 PPM Boron).
49-B 11-1-80
SCEWS Nc. 49-B TER No. 6t Date: 8/21/81 i EQUI NENT ENVIPONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 i I) Summary of new information on SCEW sheet. Nona II) Response to SER concerns. (A) l Refer to description of surveillance and preventive maintenance program , contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
f% f%
%Y Facility: Millstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.
. Simulta-System: Main Steam Operating 4
neous Plant ID No.: Time P Continuous P 1.a) Test j HY-4246, 4248 Component: Temperatur Sinulta-Solenoid valve ll20 F j ( F) Profile A neous
! 10 b '1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) 0.6 psig Profile A, H neous 10 1.b) Test Model Number: Relative 100% 100 A 1.c) Simulta-NP-831655 E Humidity (%) neous Function: Test Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N.A B N/A 1.d) Test Service: Continuous Radiation Sequential 1.94x10 6R 2 x 10 8 R C,L 1.e) Test
- Incation: Aux. Bldg. Aging Req. maint.
- EL. (-) 5'0" East Sequential performed i
Piping penetration room 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Subnergence un
*Dorumentation
References:
Notes: These components are subject to a radiation
- 1. ASCO Test Report No. AQS 21678/TR Rev. B (only) environment.
a) Appendix A Par. 5 b' Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 di Appendix A Par. 9.4.2.4.3 e) Appendix D 3 50-B 11~ I~I
SCEWS Ns. __50-B TER No. 55 Date: 8/21/81 O EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None i II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal, t III) Response to TER concerns. Same as II. 1 IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
(3 D) L. G(3 LJ cility: callstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 i 1 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUhENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Chem & Volume Cnt] . Operating Sequent ia l Plant ID No.: ZS-2525 Time Continuous Continuous C 1 Test I Component: Limit switch Temperature o Simulta-FF) 112 P P: or ile 7 A 1.a) neous Test Manufacture: NAMCO Pressure Simulta-(PSIA) 0.6 psig Profile 7 A, II 1.a) neous Test Model Number: Relative 100% 100 A 1.b) Simulta-EA180-11302 Ilumidity (%) neous Function: Test Position indication Chemical Simulta-
& valve control Spray neous Accuracy: NA NA Note 2 NA 1.c) Test Service: Limit swtich Radiation Sequential 1.64x10 6R 2.04x10 8R C,L 1.b) Test Incation: Aux. Bldg. Aging 40 yrs. Test & Gasket replacement piping penetration room 40 yrs. P.D.L. 2 Analysis required except Zone A-18 gasket (2yra) every 2 yrs.
Flood I4 vel Elev: j Above Flood Level Yes Subnergence un
- Documentation
References:
?.Otes : 1. This component is subject to a radiation
- 1. Vendor qual. report, plant file MRIR #1-26-79 (only) environment.
a) Fig. 1, Page 11 of 12 b) Page 4 of 12 2. The spray was composed of boric acid, water, sodium c) Page 8 of 12 thiosulfate, and sodium hydroxide, PH between
- 2. Wyle Report 17436-3 10 & 11 (3000 PPM Boron).
Sl-B 11-1-Gi) 1
SCEWS Ns. 51-B TER No. 65 Date: 8/21/81 O EQUIPMENT ENVIRONMUTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket Fo. 50-336 I) Summary of new information on SCEW sheet. None l II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in'oody of submittal. ( i III) Response to TER concerns. Conduit entering body of limit switch will be sealed to withstand more than the 0.6 pound differiential. l IV) Proposed corrective action and schedule. I Equipment will be incorporated into plant surveillance and preventive maintenance program. I. V) Justification for continued operation. Not applicable i
}
4 O
3 m [)\ m (d L) Facility: n111 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUAYION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION EtNIRONMENT DOCUME!!TATION REF* QUAL. OUTSTANDING METHOD ITEMS Para.Teter Spec. Qual. Spec. Qual. Simulta-System: Chem & Volume Cntl Operating 11Y-2525 neous
! Plant ID No.: Time P Continuous P 1.a) Test Component: Temperature o Simulta-Solenoid valve ( F) 112 F Profile A neous 10 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIh) 0.6 psig A , []
Profile neous 10 1.b) Test Model Number: Relative Simulta-NP-8320A185E Ifumidity (%) 100% 100 A 1.c) neous Function: Test Pilot solenoid valve Chemical i Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test Service: Continuous Radiation Sequential 1.64x106R 2 x 10 8 R C,L 1.c) Test Incation: Aux. Bldg. Aging Req. maint. EL. (-) 5'0" West Sequential performed piping penetration room - 40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-18 Flood Level Elev: Above Flood Level: Yes Sulnergence Nn
- Documentation
References:
Notes: This component is subject to a radiation
- 1. ASCO Test Report No. AQS 11678/TR Rev. B (only) environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 u) Appendix A Par. 9.4.2.4.3 e) Appendix D i 52-B 11-1-80
SCEWS No. 52-B TER No. 56 Date: 8/21/81 4 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. I III) Response to TER c oncerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program.
- V) Justification for continued operation.
- Not applicable I
i l (:)
O O O Facility: n111 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SifEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME*ITIOD ITEMS Parameter Spec. __ Qual. Spec. Qual. I Simulta-System: RBCCW Operating neous Plant ID No.: HY-6731 Time p Continuous P 1.a) Test I Simulta-Component: Temperature o 111 F A neous Solenoid valve ( F) Proffle 10 1.b) Test Manufacture: ASCO Pressu~ Simulta-(PSIA) 0.5 psig Profile ^ ' II neous 10 1.b) Test Simulta-Model Number: Relative 1.c) neous l ! Ilumidity (s) 100% 100 A Test j Function: l Pilot solenoid valve Chemical Simulta-Spray neous l l Accuracy: NA N/A B N/A 1.d) Test Service: Continuous Radiation Sequential 8.59x106R 2 x 10 8 R C,L 1.c Test Req. maint. Incation: Aux. Bldg. Aging performed Sequential EL. (-) 45'6" Test every 3 yrs 40 Years 4.4 Years PDL 1 LPSI Pump Room Zone A-2 l Flood Level Elev: i 1 Above Flood Level: Yes Submergence 1 un
- Documentation
References:
Notes: This component is subject to a radiation
- 1. ASCO Test Report No. AQS 21678/TR Rev. B (only) environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D
~~
53-B
SCEWS No. _,53-B TER No. -- - Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. I III) Response to TER concerns. Not addressed in TER.
- IV) Proposed corrective action and schedule.
Equipment will be incorporated into plant surveillance and preventiva maintenance program. l l V) Justification for continued opera *.ior. Not applicable l , ($)
% 0)
'w ()
g Facility: . 11 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME*IHOD ITEMS Parameter Spec. Qual. Spec. Qual. Syste:r.: RB M Operating Sequential Plant ID do.: ZS-6731 Time Continuous Continuous P 1 Test Component: Limit switch Temperature 111 0p Simulta-( F) Profile 7 A 1.a) neous rest Manufacture: NAMCO Pressure (PSIA) 0.5 psig Profile 7 A, H 1.d) Simulta-4 ne.ous Test Simulta-Model Number: R -lative EA740-20100 Humidity (s) 100% 100 A 1.b) neous
. rest Function:
l Position Indicat!on Chemical Simulta-f & valve control Spray neous Accuracy: NA NA Note 2 NA 1.c) Test Service: Limit switch Radiation Sequential 8.59x106R 2.04x108R C.L 1.b) Test Location: Aux. Bldg. Aging 4U yrs Test & gasket replacement EL. (-) 45'6" LPSI 40 yrs. except P.D.L. 2 Analysis required l pump room Zone A2 gasket every 2 yrs . (7 vrs:_)
- Flood Level Elev:
) Above Flood Level: Yes Subnergence un l
- Documentation Referer. 'es t Notes: 1. omponent is subject to a radiation 1.Vendorqual. report,hant file MRIR #1-26-79 Y *" * ""*"
- a) Fig. 1, Pege 11 of 12 b) Page 4 of 12
- 2. The spray was composed of boric acid, water, sodium thiosulfate, and sodium hydroxide, PH between I c) Page 8 of 12
- 2. W"le Report 17436-3 10 & 11 (3000 M Boron).
54-B 11-1-80
f
' SCEWS N254-B 64 TER No.
Date: 8/21/81
\
EQUIPMENT ENVIR0nMDiTAL QUA1.IFICATION
- SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contair ; in body of submittal. I III) Response to TEF concerns. lO i Conduit entering body of limit switch will be sealed to withstand more than the 0.5 pound differiential, l i IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O t
. - , - . - - _ , , - - . . , - - , . - . . . . . . . . . _ - - . - . _ - . - ~ . _ . . - . . . . . - . - , - - - , . , - - - - , - - _ . , - . .
. , , - , . . ~ - - , . . . , . , - - - . . - . . . . - - -
0 0 D I V V (d
, Facility: Millstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK S11EET Docket: 50-336 EINIRONMENT DOCUMENTAT N REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. _ System: RBCCW Operating Sequential Plant ID No.: ZS-6050 Time Continuous Continuous P 1 Test Component: Limit swtich Temperature o Simulta-( F) 111 F Profile 7 1.a) ntous A Test Manufacture: NAMCO Pressure Simulta-I (PSIA) 0.5 psig Profile 7 A, H 1.a) neous Test Simulta-l Model Number: Relativ 100% 100 A 1.b) neous EA740-20100 11umidity(%) Test Function: 1 Position Indication Chemical Simulta-4 & valve control Spray neous NA Note 2 . Accuracy: NA NA 1.c) Test a Service: Limit swtich Radiation Sequential 2 2.9 x 10 5 R 2.04x108R C.L 1.b) Test Incation: Aux. Bldg. 4 Aging 40 yrs. Test & Gasket reple cement j
! EL. (-) 45'6" LPSI 40 yrs. e:: cept P.D.L. 2 Analysis required Pump room Zone A2 gasket every 2 (7 yrc_) 7 2.
Flood Level Elev: Above Flood Level: Yes Subnergence nn
- Documentation
References:
Notes: 1. This component is subject to a radiation
- 1. Vendor qual, report, plant file MR1R #1-26-79 (only) environment.
4 a) Fig. 1, Page 11 of 12 b) Page 4 of 12 2. The spray was composed of boric acid, water, sodium c) Page 8 of 12 thiosulfate, and sodium hydroxide, PH between
- 2. Wyle Report 17436-3 10 & 11 (3000 PPM Boron).
- 11-1-80 55-B
I SCEWS No. 55-B - TER No. At Date: 8/21/81 d EQUIPMENT ENVIRONMDITAL QUAL.IFICATION SER/TER REVIEW Millstone Unit 2 Locket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. t III) Response to TER concerns. O Conduit entering body of limit switch will be sealed to withstand more than the 0.5 pound differiential. IV) Proposed corrective action and schedule. Equitment will be incorporated into plant surveillance and preventive maincenance program. V) Justification for continued operation. Not applicable O
O O _ O_ Facility: Millstone Nuclear Pr. 8ta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METi!OD ITEMS Parameter Spec. Qual. Spec. Qual. imulta-System: RBCCW Operating
"" "8 Plant ID No.: IIY-5050 Time P Continuous P 1.a) Test Component: Solenoid Temperature g Simulta-valve ( F) 111 F Profile A 1.b) neous 10 Test Manufacture: ASCO Pressure S i m'.il t a-(PSIA) 0.5 psig Proffle A, !! neow 10 1.b) Test Model Number: Relative Simulta-NP-8321A6E Ilumidity (s) 100% 100 A 1.c) neous Function: Test Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A 1.d) Test N/A B Service: Continuous Radiation Sequential 2.9 x 10 5 R 2 x 108 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint.
EL. (-)45'6" LPSI Sequential performed Pump room Zone A-2 40 Years 4.4 Years PDL 1 Test every 3 yrs 1 Flood Level Elev: Above Flood Level: Yes Sulnnergence Nn
- Documentation
References:
Notes: This component ic subject to a
- 1. ASCO Test Report No. AQS 21678/' Rev. B radiation (only) er.vironment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 56-B 11-1-80
--<Bms:.- - 1- a p J - - .a -M - - - _ -
SCEWS N3. 56-B TER No. 57 Date: 8/21/81 O EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None 1 II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. ( III) Response to TER concerns. l O Same as II. IV) Proposed corrective action and schedule. Eculpment will be incorporate. 2nto plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
, _.,, .,, _ . - -. . - , , . , - , . . - . . . - . . - ~ - - - . - - - - . - - - - . - * - , - _ _ _ _ _ _ _ -_ -
O O O Facility: millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT Di',SCRIPTION METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Main Steam Operating Sequential ! Plant ID No.: Time Continuous Continuour P 1 Test ZS-4250, 4251 Component: Limit swtich Temperature Simulta-( F) 112 P Profile 7 A 1.a) neous Test Manufacture: NAMCO Pressure 0.6 psig A, II 1.a) Simulta-(PSIA) Profile 7 neous Test Simulta-Model Number: Relative neous Ilumidity(s) 100% 100 A 1.b) EA180-11302 Test Function: Position Indication Chemical Simulta-
& valve control Spray neous Accuracy: NA NA Note 2 NA 1.c) Test Jervice: Limit switch Radiation Sequential 6
1.6 10 R 2.04x10 0 R C.L 1.b) Test Aux. Bldg. Aging sdSket Location: 40 yrs. replacement EL. (-)5'0" West pipe- P*D.L*
' Test &
40 yrs. except required eve ry Analysis penetration room Zone A18
- gasket (2y s.) , . . -
'~~'
Flood Level Elev: Above Flood Level: Yes Submergence Nn \
- Documentation
References:
Notes: 1.These components are subject to a radiation
- 1. Vendor qual. report, plant file MRIR #1-26-79 (only) environment.
a) Fig. 1, Page 11 of 12 b) Page 4 of 12 2. The spray was composed of boric acid, water, sodium c) Page 8 of 12 thiosulf ate, and sodium hydroxide, PH between
- 2. Wyle Report 17436-3 57-B 11-1-80
\
i SCEWS No. 57-B TER No. 65 Date: 8/21/81 O EQUIPMENT INVIRONMENTAL QUALIFICATION SER/TER REVIEW ~ Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and pr2ventive maintenance program contained in body of submittal. I III) Response to TER concerns. O Conduit entering body of limit switch will be sealed to withstand
; more than the 0.5 pound differiential.
i IV) Proposed corrective action and schedule. I l Equipment will be incorporated into plant surveillance and preventive maintenance program: V) Justification for continued operation. Not applicable O
- - - - . , . . - . - - . - - . - ~ . ~ . . - , .,.,.-,.__,.__--.,,._.,,_,-.,r,__.,_-_,.. v.., - . - , - ~ , .- , , - - - - - - , , ,-,-_,.--t__.,_.y . _ , . . - - ,, _ -
rm p %. Facility: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIROtatENT DOCUMENTATIOtt REF* QUAL. OUTSTANDING MEniOD ITEMS Parameter Spec. Qual. Spec. Qual. Main Steam Operating SI""It"- System: IIY-4 250, ne us Plant ID No.- Time 4251 P Continuous P 1.a) Test Component: Temperature Simulta-Solenoid valve ( F) 112oF Profile A 1.b) neous 10 Test Manufacture: ASCO pressure Simulta-(PSIA) 0.6 psig Profile A, 11 neous 10 1.b) Test Model Number: Relative 100% A NP-8320A185E 11umidity (%) 100 1.c) s Function: Pilot solenoid valve Chemical i Simulta-Spray neous Accurar y: NA N/A B N/A 1.d) Test Service: Continuous Radiation Sequential 1.6 x 106 R 2 x 10 8 R CL 1.e) Test Location: Aux. Bldg. Aging l Req. maint. EL. (-)5'0" West pipe Sequential performed penetration room 40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-18 Flood Level Elev: Above Flood Level: Yes Subnergence Nn t
- Documentation
References:
Notes: These components are subject to a rad!.ation
- 1. ASCO Test Report No. AQS 21678/TR Rev. B (only) environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 58-B 11-1-80 __. ._ _ _ _ ~
SCEWS ND. 58-B TER ND. 56 Date: 8/21/81 d- EQUlPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Sumary of new information on SCEW sheet.
Nove II) Response to SER concerns.(A) i Refer to description of surveillance and preventive maintenance program contained in body of submittal . ( III) Response to TER concerns. 1 Same as 11. IV) Proposed corrective action and schedule.
- Equipment will be incorporated into plant surveillance and preventive l
maintenance program. l V) Justification for continued operation. l j Not applicable l l l CE)
- - , , - - --n,,, - ,..,.,n.,,,-,-,,---,,..,,,--,,,,.--,--,-+---r--,_.,---,--.,---,,,--,,-v,-- ~ - ,. . - .-
O 0 V U F
,111ty: .allstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIRONMENT DOCUMENTATION REF* QtfAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. See Summary System: Main Steam Operating Continuous sheet Plant ID No.: IIY-4209, Time 663, 66Ba Component: Temperature See summary 3260 F Profile Solenoid operated valve ( F) 20, A 66B, 64Ba Manufacture: ASCO Pressure See summary (PSIA) 1.8 psig A sheet 66B, 66Ba Model Number: Relativ see summary WPHTX-8320A184 100% A sheet liumidity (%) Function: 56B, 66Ba Pilot solenoid valve Chemical See summary E sheet NA NA NA 56B, 66Ba Accuracy: l Service: Main Steam Radiation See summary Header Low Point Drains sheet 66B, 66Ba Location: Aux. Bldg. Aging see summary EL. 36'6" 40 yrs. P.D.L. sheet EL. 14'6" Zone A51 56B, 66Ba Flood Ievel Elev: Above Flood Level: Yes Submergence em
- Documentation
References:
Notes: 66-B 11-1-80 ?
SCEWS No. 66-B TER No. __ 5 8 Date: 6/21/81 EQUIPMENT ENVIRONMENTAL QUAL.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCE'J sheet. None l II) Response to SER concerns. (Q1. QM, T. P. H. R. A) This equipment will be replacco with .ull.y qualified devices. ? III) Response to TER concerns. O sem - IV) Proposed :orrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification f'T continued operation. Refer to corresponding equipment summary sheet. i O I t I e
. . . , - - - . - . - _ _ - . ~ ~ - . . _ _ . ._...,.._.,_m_.___..,_._..._.. . . _ _ _ _ . . _ _ . . _ . _ , . _ _ _ . _ . - - . _ _ . , _ _ _ .
66E StBetARY SEEET NO. 66B SCIW SEEET NO.
*Date:
- 8-21-81 EQUIPMENT ENVIROIOtENTAL QUALIFICATION DIscmEPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT: SOLENOID OPERATED VALVE PILOT OPERATOR FOR MAIN STEAM READER LOW POINT DRAINS HY-4209, 4193 Automatic Switch Company (ASCO)
MANUFACTURER: These components are discrepant because of the QUALIFICATION DISCRIPANCY: lack of documented qualification data. SAFETY FUNCTION AND JUSTIFICATION O FOR CONTINUED OPERATION: These components are required to operate to isolate the main steam header low point drains on a main steam isolation signal. The failure of these components to perform this function is bounded by the existing accident analysis. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. i i l i O
- - _ . . _ - . . _ . - _ _ _ - . . - . _ - - _ . . =_ . -. . ... . . .
O Ns u)
\ O kJ J
Facility: .llstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET
<- Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METI!OD ITEMS I Parameter Spec. Qual. Spec. Qual.
Main Steam Operating Continuous See Summary System: Time Sheet Plant ID No.: IIY-4193 66Ba i Component: Temperature See summary Solenoid operated valve ( F) 324 F Profile sheet 21, A 66Ba Manufacture: ASCO Pressure (PSIA) 1.6 psi 9 A See summary sheet 66Rn See summary 1 Model Number: Relative WPHTX-8320A184 Humidity (%) 100% A sheet 66Ba , Function: Pilot solenoid valve ' Chemical See summary Spray sheet NA NA 66Ba Accuracy: N/A Main Steata Radiation See summary service-Header 1.ow Point Drains sheet < 66Ba Incation: Aux. Bldg. Aging See summary El. 36' 6" 40 yrs. P.D.L. sheet Zone A50 66Ba 4 Flood Level Elev: Above Flood Level: Yes Sulma gence no
- Documentation
References:
Notes: 66-Ba 11-1-80 a
1 SCEWS No. 66-Ba i TER No. 58 Date: 8/21/81 O ' EQUIP"UT DiVIRONMLNTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. i None II) Response to SER concerns. (RPN, T, P. H R. A, QI) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding Equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment sum: nary sheet. O
66Ba
$1306ARY SEEET NO.
66Ba SCEW SEEET NO. O EQUIPMENT ENVIRONMENTAL QUALIFICATION Date: 8/21/81 DISCREPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT: SOLENOID OPERATED VALVE PILOT OPERATOR FOR MAIN STEAM HEADER LOW POINT DRAINS HY-4209, 4193 Automatic Switch Company (ASCO) MANUFACTURER: QUALIFICATION DISCREPANCY: These components are discrepant because of the lack of documented qualification data. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED UPERATION: These compo ents are required to operate to isolate the main steam header low point drains on a main steam isolation signal. The failure of chese components to perform this function is bounded by the existing accAdent analysis. Due to the desirability of long term operability of this equipu'.at and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1 O
O O _ O Facility: .. 11 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Simultaneou:; System: RBCCW ope ating Continuous Continuous P 1, 2 Test Plant ID No.: Time PS-6119 A, B, C Component: Temperature Simultaneou.i Pressure switch ( F) 110 F 160 F A 1,2 Test Manufacture: Pressure 0.4 psig 16.0 psia A, ll 1, 2 Simultaneou ; Custom Component (PSIA) Test 1, 2 Model Numoet; Relative Humidity (%) 100% 100% A Simultaneous 604-GBR2-352 S Test Function: Valve control circuit chemical Spray Accuracy: N/A NA NA i Service: Continuous Radiation N/A See Location: Aux. Bldg. Aging summary sht . EL. (-)25'6" 40 Years P.D.L. 67B Zone A1B Flood Level Elev: Above Flood Level Yes Subnergence nn
- Documentation
References:
Notes: 10-13-80 letter from Theryn Eckstein, Custom Control Sensors, to R. K. McCarthy
- 2. Custom Component Switches, Inc., Test Report QTR 604-01 67-B 11-1-80
SCEWS No. 67-B TER No. to Date: 8/21/81 EQUIPMENT DiVIRONMDiTAL QUALIFICATION SER/TER RIVIEW Millstone Unit 2 Doc.tet No. 50-336 I) Sum =ary of new information on SCEW sheet. None II) Response to SER concerns. (Q1, T-A) This equipment will be replaced with fully qualified devices. l III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. 1 Refer to corresponding equipment summary sheet. l V) Justification for continued operation. Refer to corresponding equipment summary sheet. l 3
?
G 1 e
StBGERY SERIT NO. 67B SCEW SHEET NO. 67B Date: 8/21/81 EQUIPMENT ENVIROt0GNTAL QUALIFICATION DISCREPANT EQUIPMENT SIDGERY MILLSTONE UNIT 2 EQUlPMENT: Pressure Switches PS-6119, A, B, C MANUFACTURER: Custom Component Switches (CCS) QUALIFICATION DISCREPANCY: These components lack documente?. radiation and time / temperature aging qualification data. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: These components provide low suction header pressure protection for the reactor building closed cooling water pumps. l Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. I O e
-e --,w- - y-. w-,-. y ---.-,.-=-e e v - .p..--,a.-.,.--- ,. em.. *w r.w--ws,.~w9 - , --- - - - - - - *ew - - -- - - - - es -
; O O O Facility: aallstone Nuclear Pr. Sta.
Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEntOD ITEMS Parameter Spec. Qual. Spec. Qual. Gas & Aerated Simulta-System: Liquid Radwaste Operating P Continuous P 1.a) neous I Plant ID No.: Time Test 2 HY-9126, Component: Temperature Simulta-o ( F) 112 P Profile A 1.b) neous I Solenoid valve 10 Test
! Manufacture: ASCO Pressure Profile A, 11 1.b) Simulta-0.6 psig (PSIA) neous f 10 Test l
Simulta-4 Model Number: Relative NP-8321ASE 11umidity(%) 100% 100 A 1.c) neous Test l Function: Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test .i l Service: Radiation Sequential ] Continuous 1.9 x 10 6R 2 x 10 8 R C,L 1.c) Test i Incation: Aux. BAdg. Aging Req. maint. EL. (-)5'0" West pipe Sequential performed - penetration room 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Imvel Elev: Above Flood Level: Yes Sutunergence
- un I
- Documentation
References:
Notes: 1. This component must function in a radiation
- 1. ASCO Test Report No. AQS 21678/TR Rev. B (only) environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 l e) Appendix D 68-B 11-1-80
i SCEWS 60. An_n TER No. 59 Date: 8/21/81 f () EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstene Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None i II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. () Same as II IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive > maintenance program. V) Justification for continued operation. Not applicaisle O
O O O , Facility: .llstone Nuclear Pr. Sta. Unit: Two LYSTEM COMPONENT EVALUATION WORK SilEET
, Docket: 50-336 i
EQUIPMENT DESCRIPTION EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. Gas & Aerated Simulta-System: Liquid Radwaste Operating nrous Plant ID No.: Time P Continuous P 1.a) Test IIY-7690 Component: Temperature Simu1ta-Solenoid valve ( F) 112 F Profile A neous 10 1.b) Test Manufacture: ASCO Pressure Siuulta-(PSIA) 0.6 psig Profile A, 11 neous 10 1.b) Test Model Number: Relative Simulta-NP-3320A189 E Itumidity(%) 100% 100 A 1.c) neous Furction: Test Pilot Solenoid Valve chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Servj r:e : Continuous Radiation Sequent kl 1.9 x 10 6 R 2 x 10 8 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint. El. (-) S' 0" Sequential performed 40 Years 4.4 Years PDL 1 Test every 3 yrs , Flood Level Elev: Above Flood Level: Yes Subnergence nn
- Documentation
References:
Notes: 1. This component must function in a radiation (only)
- 1. ASCO Tect Peport No. AQS 21678/TR Rev. B environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 60-Ba 11-1-80
SCEWS Ns. to g TER No. 60 Date: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 i ! I) Sumary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. l l 1 i IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable l O w c-vr =--w* mws, -me-y, ,y ,en,,m_. n-., . . _, . , ,__ _,_ _,. ,, , _ , _ _ __
O O L) m) G Facility: ...llstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SifEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METI!vD ITEMS Parameter Spec. Qual. Spec. Qual. Gas & Aerated See summary System: Liquid Radwaste Operating Continuous sheet Plant ID No.: Time 69B 2s-9126, , Component: Temperature See summary l Limit Switch ( F) 112 F A sheet 69B Manufacture: NAMCO Pressure See summary , (PSIA) 0.6 psig A, 11 ciheet
- t. 9 B l
Model Number: SL3CB2 Relative A See summary 100% j Humidity (%) sheet l Function: Valve position 69B ! indication & control Chemical See summary circuitry Spray sheet NA NA Accuracy:NA 69B 5ee summary Service: Waste Gas tank Radiation sheet inlet isolation vaive 1.94x106R C,L 69B W ation: Aux. Bldg. Aging See summary EL. (-) 5'0" West pipe sheet penetration room Zone A17 40 Years P.D.L. 698 Flood Level Elev: Above Flood Level: Yes Submergence un
- Documentation
References:
Nctes: This component must function in a radiation (only) environment. 69-B 11-1-80
SCEWS No. 69-B TER No. 66 ote: 8/21/B1 O EQUIPMENT ENVIRONMENTAL QUAI.IFICATION i SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (RPN, T. P H. R, A, QI) a This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as 11. IV) Proposed corrective action and schediile. Refer to corresponding equipment summary sheet, t V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
SUMMARY
SHEET NO. 69B SCEV SHEET No. 69B
.Date: 8/21/81 g
W EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 2 EQUIPMENT: STEM MOUNTED LIMIT SWITCH ZD-9126 Ex-Containment Gas & Aerated Liquid Radwaste Containment Isolation Valve MAVJFACTURER: (NAMCO) - National Acme Corporation QUALIFICATION DISCREPANCY: This equipment lacks documented qualification data. ( SAFETY FUNCTION AND JUSTIFICATION l'
) FOR CONTINUED OPERATION:
This equipment provides contacts for control circuit input and position indicacion for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will receive an insignificant radiation dose prior to its required control operation. l Due to the desirability of long term operability of this equipment and l in conformance with existing license requirements, it will be replaced l with fully qualified devices. Refer to Generic Replacement Schedule 1.
\
l n l
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ - - _ - _ _ _ _ _ _ - ._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ ~
'M (3
%/ 'J (Jh Facility: listone Nuclear Pr. Sta.
Unit: Two SYSTD. COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING l METIIOD ITEMS Parameter ' Spec. Qual. Spec. Qual. Gas & Aerated See System: Liquid Radwaste Operating Continuous summary Plant ID No.: Time sheet 25-7690 69Ba Component: Temperature See Limit Switch (OF) 112 p A summary sheet 69Ba Manufacture: NAMCO Pressure See summary (PSIA) 0.6 psig A, it sheet 69Ba Model Number: SL3CB2 Relative See summary 1
- A Humidity (s) sheet Function: Valve position 69Ba indication & control Chemical See summary-circuitry Spray sheet Accuracy: N/A NA NA 69Ba See summary Sarvice: Reactor coolant Radiation sheet sample valve 1.64x106R C,L 69Ba :
Location: Aux. Bldg. Aging See summary El. (-) 5' 0" 40 Years P.D.L. sheet
- Zone A18 69Ba :
Flood Level Elev: Above Flood Level: Yes Submergence Mn
- Documentation
References:
Notes-. , This component must function in a radiation ' (only) environment. 8 . i (
- O I
I i 69-Ba 11-1-80
, [-
1 SCEWS No. Aq_n3 TER No. (( Date: 8/21/81 I EQUIPMENT ENVIRONMDiTAI, QUAL.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet.
]
1 None l II) Response to SER concerns. (RPN, T P, H, R, A, QI) l I This equipment will be replaced with fully qualified devices. l I 1 i l
- III) Response to TER concerns.
1 Same as II. l l l i IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. 1 1 V) Justification for continued operation. Refer to corresponding equipment summary sheet. l l O
SIRetARY SHEET NO. 69Bm SCEW SHEET NO. 69Ba
/'N ' DATE: 8/21/81 U EQUIPMENT ENVIRONMENTAL QUALIFICATINI DISCREPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT: STEAM MOUNTED LIMIT SWITCHES ZS-7890 Gaseous & Aerated Liquid Radwaste Ex-Containment Isolation Valve MANUFACTURER: National Acme Corporation (NAMCO)
QUALIFICATION DISCREPANCY: These components lack documented qualification data. ( SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment provides contacts for control circuit input and position indication for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will receive an insignificant radiation dose prior to its required control operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, it will be replaced with fully qualified devices. . Refer to Generic Replacemer.t Schedule 1. O g , _. u. y . , - . , - - -
/~~N p U V b%
Facility: nt11 stone Nuclear Pr. Sta. Unit: TVo SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: '0-336 r EQUIDMENT DESCRIPTION EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METilOD ITEMS P:rameter Spec. Qual. Spec. Qual. See summary System: Service Water Operating Continuous slieet 70B Plant ID No.: 6307B Time TY-6308, 6307A, 6306 Conponent: Temparature See summary Solenoid valve 110"F ( F) A sheet 70B Manufacture: ASCO Pressure see summary (PSIA) 0.4 psig A, 11 sheet 70B Model Number: Relative See summary llT-8320A-102 'flumidity(%) 100t A sheet 70B Function: Pilot solenoid valve Chemical Spray See summary Accuracy: NA NA NA sheet 70B Sarvice: Radiation See summary RBCCW IIeat Exchanger N/A sheet 70B Iocation: Aux. Bldg. Aging See summary EL. (-)25'6" 40 Years P.D.L. sheet 70B Zone AIB Flood Level Elev: Above Flood Level: Yes Sulunergence Nn
- Documentation Peferences: Notes:
70-B 11-1-80
SCEWS No. 70-B TER No. 61 Date: 8/21/81
~%
(d EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TIR REVIEW Millstone Unit 2 Docket No. 50-336 I) Sunnary of new fr. formation on SCEW sheet. None
- 11) Response to SER concerns. (RDN, T, P, H. R, A, QT)
This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment sumnary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
SIBelARY SHEET NO. SCEV SHEET NO. O EQUIPMENT ENVIRONMENTAL QUA1,IFICATION Date: 8/21/81 DISCREPANT EQUIPMENT SIDMARY MILLSTONE UNIT 2 SOLENOID OPERATED VALVES W IPMENT: Pilot operating valves for HU-6306, 6307A 6307B, 6308 MANUFACTURER: Automatic Switch Company (ASCO) QUALIFICATION DISCREPANCY: These components are discrepant because they lack documented qualification data. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATIONS These components are required to open with a safety injection actuation signal. The catalog specifications for this equipment envelop the environmental parameters experienced by these components during the accident, hence the f ' environment will not impair these components in the performance of their safety function. The mantfacturer is currently reviewing the applicable components and the respective environmental profiles in order to provide documented assurance of component suitability to perform its safety function.
~ - - . ...
Due to the desirability of long term operability of this equipment ano in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. ,O
~ ~ . - - - - - . . . . _ , _ _ _ _ . . _ _ _ __ , _ _ _ _ , , _ _
O O ~ r O Facility: milstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DF.SCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING
~
METHOD ITEMS Parameter Spes. I Qual. Spec. Qual. See summary System: Service Water Operatin9 Continuous sheet 71B Plant ID No.: Time ZS-6306, 6107, 6308 i Com.onent: Temperature See summary Limit Switch ( F) 110 F
^ sheet 71B Manufacture: NAMCO Pressure A, H Sec summary 0.4 psig (PSIA) sheet 71B i
! Model Number: D-2400X Relative See summary 100% A Humidity (%) sheet 71B Function: Position Indication & Control Chemical See summary
- Circuit Spray sheet 71B Accuracy
- NA NA NA see summary i Ssrvice: Limit switch Radiation sheet 71B NA I4 cation: Aux. Bldg. Aging See summary EL. (-)25'6a 40 Years P.D.L. sheet 71B Zone AIB Flood Level Elev:
Above Flood Level: Yes Submergence
! Nn
- Documentation
References:
Notes: 1
< t 1
71-B 11-1-80 J
SCEWS No. vi_n TER No. ny Date: 8/21/81 O EQUIPMENT ENVIRONhENTAL QUA1.IF1 CATION SER/TER REVIEW Millstone Unit 2 Docu t No. 50-336 I) Summary of new information cn SCEW sheet. None II) Response to SER concerns. (RPN, T. P, H. R, A QI) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer t- torresponding equipment summary sheet. O
StBetARY SEEET NO. 71B SCEW SHEET NO. 71B
' Date: 8/21/81 f'J'n EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 2 EQUIPMENT: STEM MOUNTED LIMIT SWITCHES ZS-6306, 6307, 6308 - Service Water Supply Isolation to the RBCCW Heat Exchangers National Acme. Corporation (NAMCO) 1 QUALIFICATION DISCREPANCY: l SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPuRATION: O) x This equipment provides contacts for control circuit input and position indication for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject to an environment which is enveloped by the equipment catalog specifications. l Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. l l
--,mr. - - .-*-.o -e.-y -- p% _,..-4 .e.y
,p , , , - ,,,3 -- -, - -w,__ y - -.,--- .
O C) , V(~N. V U Facility: ..Allstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUME! TION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Close & stay See summary System: Service Water Operating closed on sheet 72B Plant ID No.: Time SIAS & SLB liY-6438, 6439 outside entmt. Component: Temperature 4 way solcnoid valve Profile See summary ( F) 155 F sheet 72B
- 22, A Manufacture: ASCO Pressure See summary (PSIA) 0.5 psig A, H sheet 72B Model Number: Relative 100% See summary HT-834 81 A Humidity (%) sheet 72B Function, Pilo' solenoid valve Chemical See summary Accuracy: NA NA NA Service: TBCCW llX inlet Radiation See summary isolation NA sheet 72B Incation: Turbine Bldg. Aging
' " See summary gone T10 40 Years P.D.L. sheet 72B Flood Level Elev:
Above Flood Level: Yes Subnergence nn
- Documentation
References:
Notes: 72-B 11-1-80
SCEWS N3. 72-8 TER No. 6? Date: 8/21/81 EQUIPMENT ENVIRONMB'TAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. Nsne II) Response to SER concerns. (RPN, T. P, H, R, A, QI) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. l V) Justification for continued operation. Refer to corresponding equipment summary sheet. l l O
i 72B SI3enRY SEEET NO. 72B SCEV SHEET NO. s O' EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDenRY MILLSTONE UNIT 2 SOLENOID OPERATED VALVES EQUIPMENT: Pilot Operators for Valve No. (HV-6438, 6439)
#1, 2 6 3 turbine building closed cooling water heat exchanger inlet isolation valves MANUFACTURER: Automatic Switch Company (ASCO)
QUALIFICATION DISCRIPANCY: These components lack documented qualification data. I SAFETY FUNCTION AND JUSTIFICATION O ron costtwuto ortair o": These components function as pilot operating mechanisms for TBCCW valves outside centainment. These valves are required to close on a SIAS. The catalog specifications for this equipment envelop the environmental parameters experienced by these components during a MSLB, therefore, the environment will not impair these components in performance of their safety function. The manufacturer is currently reviewing the subject components and the respective environmental profiles in order to provide documented assurance of component suitability to perform its safety function. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. O
% (Q (V
(Q> U 4 4 Facility: ,11 stone Nuclear Pr. Sta. Unit. Two SYSTEM COMPONENT EVALUATION WORK SHEET l Docket: 50-336 e EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING ME'IHOD ITEMS Parameter Spec. Qual. Spec. Qual. Intermit-System SI E. CNTMT SPRAY Operating inte 1. tent-30 min Note 1 1.a) sequential Plant ID No.: Time test j HV3008, !!V3009 cgeg"esfor Component: Valve Motor Temperature , Operators ( F) NA Manufacture: l Pressure Limitorque (PSIA) i NA j Model Number: Operator Relative S/N 152444, 152443 Humidity (%) i Function: Operators NA For CS 16.lA, 16.1B Chemical Spray Accuracy: Not required NA Service: Containment sump Radiation sequential
; recirculation 8.6 x 106 R 2.04x10 8R C.L 2.a) test Iocation: Aux. bldg. Aging plant 4 ! el. (-)45'6" Zone A2 sitaulated design 1.b) sequential 40 Yrs. 40 yrs. life test i'
Flood Level Elev: Above Flood Level: Yes Suhnergence un
' Documentation
References:
Notes: 1
- 1. Limitorque Test Report 600198 If:'/69 to 4/29/60 1. Valve must open on SRAS and stay open under radiation
, and Addendum 1 (only) environment. Ref. FSAR 6.2.3.1, sys. des ription.
a) page 4 i 2. L mit que Test Report 600376A,4/26/76 tn 8/30/72 a) Pr. r . 2.1
. 83-B 11-1-80
SCEWS Ns. 83-B TER No. 70A Date: 8/21/81 EQUIPMENT ENVIRONMENTA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Qualified life is greater than or equal to the plant design life. The above ref erenced surveillance program will periodically verify the aging analysis. FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable -)
l O O O
! Ftcility: Millstone Nuclear Pr. Sta.
Unit Two SYSTEJ4 COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING j EQUIPMENT DESCRIPTION MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Chem. & Vol. Cntl - Operating Note 1. 200 1.a) sequential , Plant ID No.: CII 501 Time cycles Note 2 test Component: Valve Motor Temperature Operator ( F) i NA Manufacture: Limitorque Pressure i (PSIA) NA ) Model Number: Operator Relative l S/N 134086 Humidity (%) Function: Operator NA i for Cil501 Chemical i Spray Accuracy: Not required NA
! Service: Volume control Radiation 8.32x10 5R 0
2.04x10 R C,L 1.b) sequential ! tank discharge valve test i Incation: Aux. Bldg. Aging simulated plant El. (-)25'6" Zone A9 0 yrs. 40 yrs. design 1.c) sequential life test i 4 Flood Ievel Elev: i Above Flood Level: Yes Suhnergence un
- Documentation
References:
Notes:
- 1. Limitorque Test Report B0003 11/13/74 to 1/23/75 1. Valve must close and stay closed under radiation i
a) par. 2.1.3 (only) environment. b) par. 2.3 2. FSAR Sec. 9.2.3.4 & P & ID 25203-26017 c) par. 5.0 4 I
. 84-B 11-1-80
f SCEWS No. 84-B TER *io. 70B _ Date: 8/21/81 O EQUIPMENT ENVIRONMENTA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. i SCEWS 84-B not addressed in SER. l ( III) Response to TER concerns. O FRC should review documentation. 1 IV) Proposed corrective action and schedule. equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable 1 0
O Fccility: **illstone Nuclstr Pr. Sts. O O Unit: Tw SYSTEM COMPONENT F. UATION WORK SHEET Docket Su -336 EQUIPMENT DESCRIPTION ENVIRONMENT Note 3. DOCUMENTATION PEF
- QUAL. OUTSTANDING ITEMS
. METHOD Qual. Parameter Spec. Qual. Spec. tystem Chem. & Vol. Cntl Operating 2 hrs. max. Note 4 Note 2 3.a) sequential Plant ID No.: P18A, P18B Time Note 2 test P18C Component: Pump Motors Temperature 460V (Or) NA Manufacture: Westinghouse Pressure (PSIA) NA Model Number: Cat. Type Relative TCDP Humidity (%)
- Function: Pump Drive NA
' chemical Spray Accuracy: !?ot required .
NA Service: Charging Pumps Radiation 5.25x10 5R 2x108R C,L 2.a) sequential test Incation: Aux. Bldg. Aging sequential El. (-)25'6" Zone A9 40 yrs. 40 yrs. 1. 2.b) test Flood Imvel Elev: Above Flood Imvel: b:s Submergence un fDocumentation
References:
Notes:
- 1. Combustion Engineering' Spec. 3072-PE-403 and 1. Originally installed pumps are in process of being SYS80 PE-403 replaced. Completion is planned for late 1981.
- 2. WCAP-9112, Qualification of Westinghouse Medium 2. Pumps must run until the boric acid tanks are empty Motor and Gearing Div. Class lE motors (2 hrs. max.) Ref. W. G. Counsil to R. Reid letters a) Par. 2.5.4, Page 13 b) Par. 2.4, Page 12 3/22/79 and 4/9/79.
- 3. Operating and Maintenance Instructions - 3. Motors trust function in n radiation (only) environment.
Reciprocating Charging Pump NP18-3.1 TFS 4. Motor is designed for continuous operation, a) Sect. iii, Form A-2 Temp. rise test duration was 5.5 hrs. 85-B 8-21-81
SCEWS No. 85-B TER No. 7I Date. 8/21/81 O ' EQUIPKENT ENVIRONMENTAL QUALIFICATION SER/TEF. REVIEW Millstone Unit 2 Docket Mc 50-336 A I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (RPN, A,) 2 of 3 pumps now in service. The third pump will be replaced by 1-1-82. Technical Specifications only require operability of two (2) pumps. Refer to dtscription of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. FRC should review documentation. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O O O Ftcility: Millstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 i EOUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING l METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Systems Chem. & Vol. Cntl. . Operating continuous continuous 1, 2 Plant ID No.: PS224X, Time
,PS224Y, PS224Z Component: Temperature Vacuum switches (OF) 110 F 160 F A 1, 2
, Manufacture : Cus t om Pressure 1 Component (PSIA) 16.0 PSIA A,H 1, 2 y 0.4 PSIC f Model Number: Relative 604 VBI-351S Humidity (%) 100 A Ftu.ction : Valve / pump j control Cheanical Accuracy: N/A NA NA I Service : P18A, B, C Radiation suction header N/A Incation: Aux. Bldg. Aging See summary El. (-) 2 5 ' 6" 40 Years P.D.L. sheet 86B Zone AlB Flood Ievel Elev: 4 Above Flood Level: Yes Subnergence
# Documentation Refe,rences: Notes l 1. 10-13-80 letter from Theryn Eckstein, ! Custom Control Sensors, to R. K. McCarthy
- 2. Custom Component Switches, Test Report QTR 604-01 86-B 11-1-80
SCEWS No. 86-B TER No. 77 Date: 8/21/81 ; O EQUIPMENT ENVIRONMINTAL QUA1.IFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of t.ew inf ormation on SCEW sheet. None II) Response to SER concerns. (QI,QM) This equipment will be replaced with fully qualified devices III) Response to TER concerns. O- Same as II. I IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. l V) Justification for continued operation. Refer to corresponding equipment summary sheet. l l O
SUMMAkY SHEET NO. 86B SCEW SHEET NO. 86B
'v' EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMEP, SIDEARY MILLSTONE INIT 2 Pressure Switches PS-224X, i, Z EQUIPMENT:
Charging Pump Suction Header Pressure MANUFACTURER: Custom Component Switches (CCS) QUALIFICATION DISCREPANCY: These components lack documented radiation and time / temperature aging qualification data. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: These components provide low suction header pressure protection for the charging pumps. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified desices- Refer to Generic Replacement Schedule 2. t i i l l O] r 1 l l
r o m Facility: rullstone Nuclear Pr. Sta. Unit: Two SYSTEM COMFCNENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT Note 2. DOCUMENTATION REF* QUAL. OUTSTANDIliG METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. Intermit-System: SIS & Cont. Spray Operating Note 1. tent-30 min Note 3.
.a seque d al Plant ID No.: !!V3021 Time cycles for test HV3022 9 hrs.
Component: Valve Motor Temperature Operator (01) NA Manufacture: Limitorque Pressure (PSIA) NA Model Number: Operator Relative S/N 145931 Ilumidity(%) Function: Operator NA for CS 4.lA chemical Accuracy: Not required A Service: Cont. Spray Radiation sequential Stop valve 2.57x106R 2.04x108R C,L 2.a) test Incation: Aux. B'dg. Aging simulated plant El.(-)5'0" Zone A18 40 Yrs. 40 yrs. design 1.b) sequential (HV3021), A17(HV3022) test life Flood Level Elev: Above Flood Level: Yes Submergence Nn
- Documentation
References:
Notes:
- 1. Valve must open and stay open. May require to 1- Limitorque Test Repo:t 600198 1/2/69 to 4/29/69 close after containment spray is terminated.
and Addendum 1 2. Valve must function in a radiation (only) environment. a) page 4 3. FSAR 6.4.3.1 & P & ID 25203-16017 b) page 5
- 2. Limitorque Test Report 600376A,4/26/72 to 8/30/72 a) Par. 2.1 89-B 11-1-80
SCEWS Ns. 89-B TER No. 70C Date: 8/21/81 EQUIPMENT ENVIRONMDITA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) i Refer to description of surveillance and preventive maintenance program contained in body of submittal. i III) Response to TER concerns. ( Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify i the aging analysis.
- FRC should review documentation.
IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O gy--.~ -e-- -. ,, ~n ,,,-~,er,,.,,em.,, - - , ,,-.v.-,. ,,,e-.- , , , , , ,n,, , ,.,,m,_m . y -- , , , ., - -._.,-.r.p.,.,,a,,aew , . , , , , , , , _ - - . , ,,----------m,
N tO Q Ftcility: .llstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION FORK SHEET Docket: 50-336 i EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS l Parameter Spec. Qual. Spec. Qual. ~ See summary System: Cntmt. Press. Operating continuous 2 sheet 91B Plant ID No.: PT-8113, Time 2 8114, 8115, 8116 Component: Temperature See summary 1 Pre.ss. Transmitter (or) og sheet 91B i Manufacture: Foxbor Pressure See summary (PSIA) sheet 91B 0.6 PSIC AH Model Number: Relative See summary E-llDM Humidity (%) sheet 91B 100% A Function:
' Chemical see summary ,
spray sheet 91B Accuracy: NA NA Service: Cntmt. Press. Radiation Sequential sheet 91B 2.22x10 6R 1 x 10 7 R C 1 Test Aux. Bldg. Aging See summary Incati El. :5 ' 10" A17,A18 sheet 91B 40 Years P.D.L. Flood Level Elev: Above Flood Level: Yes Submergence un I
' Documentation
References:
Notes: These components must function in a radiation
- 1. Foxboro Test Report T2-1075, T3-1097 (only) environment.
- 2. MPII FSAR Table 7.5.2 91-B 11-1-80
SCEWS Ns. '>1-B TER Ns. 71 Date: 8/21/81 . EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) This equipment will be replaced with fully qualified devices. III) Response to TER concerns, i O s me - 11. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet, i V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
StBelARY SEEIT NO. 913 SCEW SHEET NO. 91B
'Date: 8/21/81 b EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT.
Containment Pressure Transmitters PT-8113, 8114, 8115, 8116 MANUFACTURER: Foxboro Model Ell-DM These components lack documented qualifications QUALIFICATION DISCREPANCY: concerning Time / temper..ture aging, SAFETY FUNCTION AND JUSTIFICATION pd FOR CONTINUED OPERATION: This equipment provides signal input for engineered safety features actuation of the containment spray, enclosure building filtration, containment isolation and emergency core cooling systems on a high containment pressure condition. The catalog specifications for this equipment envelop the environmental parameters experienced by these components during the accident, therefore, the environment will not impair these components in performance of their safety function. Two additional environmentally qualified channels of containment pressure monitoring have been installed for post accident monitoring. Due to the present age of this equipment, and the severity of the as new test, assurance is provided that the equipment will perform its function. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule.2.
.-. - _ .-. --.- . ..-~ - --.- ,.-.-. --. --. .--.- . -.
k J SCEWS No. 92-B TER No. Date: 8/21/81 4 O EQUIPMENT ENVIRONMENTAL QUALIFICATION r t s 1 SER/TER REVIEW Millstone Unit 2 i j Docket No. 50-336 i i I) Summary of new information on SCEW sheet. ! This SCEWS has been deleted. It is redundant to SCEWS 43-B 1 II) Response to SER concerns.
'.ocated in Appendix "C".
i 1 III) Response to TER concerns, i Not addressed in TER. ! IV) Proposed corrective action and schedule. l i I I f V) Justification for continued operation. } i l i i i O I i l , i
O O_ O i Facility: ..llstone Nuclear Pr Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 t EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.
*" #~
Systen: Safety injection Operating " Plant ID No.: Time Test HY-659, HY-660 P Continuous P 1.a) Component: S len id Temperature Simulta-operated valve (DF) Profile neous N/A 10 N/A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous N/A 10 N/A 1.b) Test Model Number: Relative Simulta- . NP-831655E Humidity (%) neous { Function: Pilot scilenoid N/A 100 N/A 1.c) Test valve ' Chemical Simulta- ) Spray neous Accuracy: N/A N/A B N/A 1.d) Test I Ssrvice: Safety injection Radiation Sequential Pump discharge bypass 6.37x10 6R 2 x 10 8R C,L 1.e) Test header
! I4 cation: Aux. Bldg. Aging Reo. maint. , El. (-) 45' 6" Sequential perfor:ned 40 Years 4.4 Years PDL 1 Test every 3 yrs -
Flood Level Elev: Above Flood Level: Yes Suhnergence nn
- Documentation
References:
Notes: This component is subject to a
- 1. ASCO Test Report No. AQS 21678/TR Rev. B radiation only environment.
< a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A l'ar. 9.4.2.4. 3 e) Appendix D 94-B 11-1-80
M SCEWS No. 94-B 1 2 TER No. qq Date: 8/21/81 0 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2
! Docket !Io. 50-336 I) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) i Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. 4 O Same as 11. { IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. i l V) Justification for continued operation, Not applicable j f , O f
r\ l')
\
t.) Q'%./ NJ Pccility: .._llstone Nuclear Pr. Sta. Unit: Two SY.3 TEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 ENVIRONMENT DOCUME! ATION REF* QUAL. OUTSTANDING EQUIPMENT DE.dCRIPTION METHOD ITEMS Spec. Qual. Spec. Qual. Primary Makeup , jl Parameter Simulta- f System: Water Operating neous Plant ID No.: HY-7311 Time P Continuous P 1.a) Test Component: Solenoid Temperature Simulta- ) operated valve f F) Profile neous 112 F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,11 1.b) Test Simulta-Model Number: Relative "COUS NP-8321 AS E Humidity (%) Function: Pilot solenoid 100 100 A 1.c) Test - valve Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test 9 i Service: Primary makeup Radiation Sequential , water to quench tank 1.94x106R 2 x 108 R C,L 1.e) Test '. Location: Aux. Bldg. Aging Req. maint.
- l l El. (-) 5' 0" . Sequential performed [ !
40 Years 4.4 Years PDL Test every 3 yrs j l Zone A-18 1 l Flood Level Elev: Above Flood Level: Yes Subnergence No l
- Documentation
References:
Notes: !
- 1. ASCO Tert Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 8
c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 t l e) Appendix D , o i I 95-B 11-1-80 s i
' ' ' ~
y
- - - - ~
g
SCEWS Ns. 95-B TER No. so Date: 8/21/81 C) EQUIPMENT DIVIRONMDITAL QUALIFICATION SER/TER REVIEW 3 Millstene Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance nrogram, i V) Justification for continued operation. Not applicable i O
O O _. O Ftcility: ...I1 stone Nuclear Pr. Sta, Unit: Two SYSTEM COMPO7ENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONFENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Ctat. Air Simulta-System: Recirculation Operatin9 neous Plant ID No.: HY-6073, Time P Continue"- P 1.a) Test 6077 Component: Solenoid Temperature Simulta-valve ( F) Profile neous
. 112*F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test I""IE ~
Model Number: Relative
"" "8 NP-331655E Humidity (%)
100 100 A 1.c) Test Function: Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Ctat. air recirc Radiation Sequential cooled inlet 2.42x106R 2 x 108 R C,L 1.e) Test i Incation: Aux. Bldg. Aging Req. maint. El. (-) 5'0" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Subnergence vm
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 c) Appendix D 96-B 11-1-80
SCEWS N2. 96-B TER No. ss Date: 8/21/81 O EQUIPMENT ENVIRONML'NTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. Nonc II) Response to SER concerns.(A) Refer to description of surveillance and preventi?e maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surve$11ance and preventive unintenance program. V) Justification for continued operation. Not applicable O
( (D w) 0 N.J Facility: .llstone %: clear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SifEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING , EQUIPMENT DESCRIPTION ENVIRONMENT ME'n!OD ITEMS Parameter Spec. Qual. Spec. Qual.
"" "~
System: Cntmt. Air Recirc Operating " " I!Y-6084, Time Plant ID No.: P Continious P 1.a) Test Simulta-Ccmponent: Solenoid Valve Temperature neous ProfJle ( F) 1.b) ll2*F 10 A Test A CO Pressure Manufacture: Simulta-(PSIA) Profile neous 0.6 PSIG 10 A ,il 1.b) Test Simulta-Model Number: Relative
""U"8 MP-831655E Humidity (%)
Function: Pilot solenoid 100 100 A 1.c) Test valve Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Ctmt. air recirc Radiation Sequential 6 8 cooler control valve 2.56x10 R 2 x 10 R C,L 1.e) Test Aging Req. maint. Location: Aux. Bldg. Sequential :perforr.ed El. (-) 5'0" 40 Years PDL 1 Test every 3 yrs Zone A-18 4.4 Years Flood Level Elev: l Above Flood Level: Yes i Subnergerace m, 1.
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4. 3 e) Appendix D l
97-B 8-21481 o
1 l i SCEWS ND. 97-B TER No. 55 rate: 8/21/81 i EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. Removed reference to HY-6092. II) Response to SEE concerns. (A) Pefer to description of surveillance and preventive maintenance program contained in body of submittal. III) Respc' e e- TFP. c. scerns. Same as II. 1 IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O O O: 9 q) - -- v Facility: .11 stone Nuclear Pr. Sta. Unit: Two SYSTEri COMPONENT EVALUATION WORK S!!EET Docket: 50-336 EQUIPMENT DESCRIPTION EfNIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METiiOD ITEMS Parameter Spec. Qual. Spec. Qual. Sample & a s Simulta-System: Effluents Operating Plant ID No.: HY-6092 Time 4 P Continuous P 1.a) Test Component: Solenoid Temperature Simulta-( F) Profile neous operated va*ves 112,F 10 A 1.b) Test Menufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIC 10 A ,il 1.b) Test 1 Model Number: Relative Simulta-NP-831655E Ilumidity(s) neous 1 Function: Pilot solenoid 100 100 A 1.c) Test valve Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Sample & Cas Radiation 1.02X106R 2 x 10 8 R C ,. L 1. e .) Sequential effluent filter stop Test valve
; Incation: Aux. Bldg. Aging Req. maint.
El. (-) 5' 0" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Abo're Flood Level: Yes Suisnergence
- Nn l
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2
- ) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3
.t) Appendix D 98-B 11-1-80
SCEWS Ns. 98-B TER No. ss Date: 8/21/'1 O EQUIPMDiT INVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. .i None II) Response to SER concerns. (A) Refer to description of surveillasce and preventive maintenance program contained in body of submittal. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O O O Facility: .llstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET Cocxet: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* Qf ,AL . OUTSTANDING
'ETilOD ITEMS Parameter Spec. Qual. - Spec. Qual. _
Instrument Air Simulta-System: Operating Plant ID No.: HY-7083 Time P P 1 Tm Component: Temperature Simulta-Solenoid Operated valve ( F) Profile neous 112*F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIC 10 A,ll 1.b) Test Model Number: Relative Simulta-NP-8321 A5 E Humidity (%) neous Function: Pilot valve 100 100 A 1.c) Test Chemical i Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Ctnt. instrumeni: Radiation Sequential air block valve 1.65x10bR 0 2 x 10 R C,L 1.e) Test Iocation: Aux. Bldg. Aging Req. maint. El. (-) 5"O" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Levelr Yes Submergence un
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4. 3 e) Appendix D 99-B 11-1-80
S"EWS No. 99-B TER No. , so Date: 8/21/81 O EQUIPMENT DVIRONMGTAL QUALIFICATION SER/TER REVIEW
.Villstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. [) Same as II. IV) Proposed corrective action and schedule. l Equipment will be incorporated into plant surveillance and preventive maintenance program. l V) Justification for continued operation. Not applicable O
O O O , Facility: _llstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EN' %ONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METl!OD ITEMS Parameter Spec. Qual. Spec. Qual. System: Simulta-Primary Drain Operating neous i Plant ID No.: HY-9016 Time P Continuous P 1.a) Test Component: Solenoid Temperature Sinculta-operated valves ( F) Profile neous x 112*F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIC 10 A,Il 1.c) Test i Model Number: Relative Simulta-
! NP-8321 A5E Humidity (s) neous Function: Pilot valve 100 100 A 1.d) Test
- ' Chemical Simulta-Spray neous 1
Accuracy: N/A N/A B N/A 1.d) Test Service: Primary drain Radiation Sequential tank discharge isol. 2.12x106R 2 x 10 8 R C,L 1.e) Test valve Incation: Aux. Bldg. Aging Req. maint.
- El. (-) 5' 0" Sequential pe rfo rmed 4.4 Years I Zone A-18 40 Years PDL 1 Test every 3 yrs ,
Flood Level Elev: I Above Flood Level: Yes Subnergence Nm
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D LOO-B 11-1-80
SCEWS Ns. 100-B TER No. sq Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 l I) Sununary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. I III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable 0
f
'% w/
I~) V Facility: listone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. RCS Simulta-System: Operating Plant ID No.: Time os HY-505 P Continuous P 1.a) Test Component: S len id Temperature Simulta-operated valves gor)
- Profile neous 112*F 10 A 1.b) Test Manufacture: Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,Il 1.b) Test Model Number: Relative Simulta-NP-8321ASE Humidity (%) neous Function: 100 100 A 1.c) Test Pilot valve Chemical Simulta-Spray neous Accuracy: N/A B N/A 1.d) Test Service: RCP Bleed Off Radiation Sequential Isolation valve 2.12x106R 2 x 10 8 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint.
El. (-) 5 ' 0" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Subnergence Nm
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2
- c. ) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 a) Appendix D 102-B 11-1-80
4 SCEWS No. 102-B TER No. 59 Date: 8/21/81 EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER cencerns. (A) Refer to description of surveillance and preventive safetenance program contained in body of submittal.
..II)
. Response to TER concerns.
Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. 1 V) Justification for continued operation. Not applicable l l I O
. = - . . - _ . _ . _ -. .
J A SCEWS No. 103-B TER No. 59 Date: 8/21/81 lO EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW l Millstone Unit 2 Decket No. 50-336 l 4 I) Summary of new information on ECEW sheet. l This SCEWS is deleted as it is redundant to SCEWS 68-B. t I l II) Response to SER concerns. I a i 1 ' III) Response to TER concerns. 1 O l IV) Proposed corrective action and schedule, i l V) Justification for continued operation. i i f O H w,-..-..-.r+.e---.--.e,..-..m-,,%,,ww,,.r ,-aww,,,.m,--- n.,- w ,,. m ,-e, -,r.w.-+..ym ,,y,.,
I SCEWS No. 104-B TER No. __ 55 Date: 8/21/81 1 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 a l Docket No. 50-336 7 i i I) Summary of new information on SCEW sheet. This SCEWS is deleted as it is redundant to SCEWS 50B. II) Response to SER concerns. i III) Response to TER concerns. , O 4 1 t IV) Proposed corrective action ano schedule. l V) Justification for continued operation. l l l l I 1 I I O I
SCEWS No. 104-B TER No. 55 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW M111stune Unit 2 Docket No. 50-336 { l l I) Summary of new information on SCEW sheet. ; I
! This SCEWS is deleted as it is redundant to SCEWS 50B.
4 . 1 i II) Response to SER concerns. i 1 i l III) Response to TER concerns. O 1 l I IV) Proposed corrective action and schedule. i t t [ V) Justification for continued operation. I f O (
Og
\._/ v
/ (]/
/
Facility: Listone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SIIEET
. Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _
Simulta-System: Ctmt. Air Operating neous Plant ID No.: HY-6080, Time P Continuous P 1.a) Test 6088 Component. : Solenoid Temperature Simulta-operated valve ( F) Profile neous 4 112*F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIC 10 A,Il 1.b) Test Model Number: Relative Simulta-NP-831655 Ilumidity (%) neous runction: Pilot valve 100 100 A 1.c) Test , Chemical Simulta-Spray neous 1 Accuracy: N/A N/A B N/A 1.d) Test ? , Service: Ctat. air recirc Radiation Sequential cooler control valve 1.94x106R 2 x 10 8 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint. El. (-) 5' 0" Sequential performed l'40 Years 4.4 Years PDL 1 Test every 3 yrs i Flood Level Elev: Above Flood Level: Yes Submergence Nn
- Documentation
References:
Notes:
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 J-) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 4
lO6-B 11-1-80
SCEWS N3, 106-B TER No. 63 Date: 8/21/81 EQUIPMENT DNIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. (f III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable 1 l
1 Facility: o Lilstone Nuclear Pr. Sta. O O Unit: Two Docket: 50-336 SYSTEM COMPONENT EVALUATION WORK SHEET t EQUIPMENT DESCRIPTION ENVIRONMEt?"' DOCUMENTATION REF* QUAL. OUTSTANDING + Parameter METilOD ITEMS Spec. Qual. Spec. Qual. System: Ctmt. Air Operating Plant ID No.: ItY-6072, Simulta-OGb Time neous P Contiuuous P 1.a) Test Component: Solenoid Temperature operated valve (oF) Simulta-Pro file neous Manufacture: ASCO Pressure (PSIA) Simulta-5 Profile neous 0.6 PSIG 10 A,H 1.b) Test Model Number: Relative 4 NP-831655 Simulta-Ilumidity(s) neous { Function: Pilot valve 100 100 A 1.c) Test Chemical Spray Simulta-Accuracy:
,p neous N/A B N/A 1.d) Test Sarvi,ce : Ctmt. Air recirc cooler inlet Radiation i Sequential 1.16x106R 2 x 10 8" C,L 1.e) Test i Aux. Bldg.
Q^,tioq: , , , Agin9 - Req. maint. Zone A-17 40 Years Sequential performed _ 4.4 Years PDL L Test every 3 yrs
, Flood Level Elev:
Jbove Flood Level: Yes Subnergence w Nn i
' Documentation
References:
Notes: This component must function in a
- 1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. 5 b) Appendix A Fig. 9.2 radiation (only) environment..
c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D i 107-B 11-1-80
SCEWS Ns. 107_n TER No. 63 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket Fo. 50-336 I) Summary of new information on SCEW sheet. None II) Lesponse to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. 4 t III) Response to TER concerns. O Same as II. l IV) Proposed corrective action and schedule. Equipment will be incorporated into riant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable 1 O l 1
O O O Facility: Listone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT E ht,UATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION FNVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METIIOD ITEMS Parameter Spec. Qual. Spec. Qual. N2 Simulta-System: Operating neous Plant ID No.: 11Y-7312 Time P Continuous P 1.a) Test Component: Pilot Temperature Simulta-solenoid valve (op) Profile neous 112'F 10 A 1.b) Test Manufw ture: Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,Il 1.b) Test
" ~
Model Number: Relative NP-8320A189E 11umidity (s) Fungtion: 100 100 A 1.c) T Pilot valve Chemical Simulta-Spray neous Accuracy: N/A B N/A 1.d) Test Service: N2 stop valve Radiation Sequential to S.I tanks 1.94x106R 2 x 10 8R C,L 1.e) Test Location: Aux. Bldg. Aging Req. maint. El. (-) 5'0" Sequential performed Zone A-17 40 Years 4.4 Years PDL 1 Test every 3 yre Flood Level Elev: Above Flood Level: Yes Sulunergence Nn
- Documentation
References:
Notes: This component must function in a
- 1. ASCO Test Report No. AQS 21678/TR Rev. B radiation (only) environment, a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4. 3 e) Appendix D 108-B 11-1-80
d SCEWS N2. 108-B TER No. An Date: 8/21/81 Cl v EQUIPMENT ENVIRONM UTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of survef1. lance and preventive maintenance program contained in body of submittal. ( III) Response to TER concerns. ( Same as II. IV) Preposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
_ _ _ _ = _ _ - - .-. - . = - _ _ . - - . . . _ _ _ . . . _ . _ _ _ . - - . ~ . . - . - I SCEWS No. 109-B f i TER No. 60 l) Date: 8/21/81 i EQUIPMENT ENVIRONMENTAL QUALIFICATION i i SER/TER RZVIEW Millstone Unit 2 l; Docket No. 50-336 t I) Summary of new information on SCEW sheet. i j l This SCEWS is deleted as it is redundant to SCEWS 68-Ba. I I . II) Response to SER concerns. t i i i l l, l l III) Response to TER concerns. j I I f IV) Proposed corrective action and s:hedule. l V) Justification for continued operation. I i I l l ()
O O - O Facility: Listone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EtNIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. J Cn tm t . Surnp Simulta-System: Operatin9 neous " Plant ID No.: Igy-9150 Time P Continuous P 1.a) Test Component: Solenoid Temperature Simulta-operated valve ( F) Profile neous ll2*F 10 A 1.b) Test Manufacture: ASCO Pressure Simulta-(PSIA) Profile neoud 0.6 PSIG 10 A,H 1.b) Test Model Number: Relative Simulta-NP-8321A5E Ilumidity (%) neous Function: Pilot valve 100 100 A 1.c) Test chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Ctmt sump Radiation Sequential isolation valve 1.57x10 6R 2 x 10 8 R C.L 1.e) Test Location: Aux. Bldg Aging Req. maint. El. (-) 5'0" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev: Above Flood Level: Yes Sutanergence , flm
- Documentation
References:
Notes: This component must function in a
- 1. ASCO Test Report No. AQS 21678/TR Rev. B radiation (only) environment.
a) Appendix A Par. 5 b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4. 3 e) Appendix D 1 110-B 11-1-80
SCEWS Ns. 110-B TER No. sg Date: 8/21/81 EQUIPMENT DVIRONM ST/.L QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. III) Response to TER concerns. [~ Same as II. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
O O O Facility: 11 stone Nuclear Pr. Sta. . Unit: Two SYSTEM COMPONENT EhnUATION WORK SHEET Docket: 50-336 EtNIRON!iE:tr DOCUMENTATION REF* QUAL. OUTSTANDING l EQUIPMENT DF~ 41PTION i METHOD ITEMS [ Parameter Spec. Qual. Spec. Qual. See System: Cntmt. Recire Operating continuous summary aht. Plant ID No.: ZS-6080, Time 112B ZS-6084 , ZS-6088, 6092 Component: Limit switch Temperature See summary ( F) sheet 112B 1120F A NA'tCO 5cc sununar y Manufacture: Pressure sheet 112B (PSIA) 0.6 PSIG A.H SL3C See summary Model Number: Relative Humidity (%) sheet 112B 100 A Function: Position ind. j valve control Chemical See summary j Spray sheet 112B Accuracy: N/A NA NA dee summary Szrvice: Cntmt. air Radiation sheet 112B recirc cooler control 6 valve 2.12x10 R C,L Incation: Aging See summary Aux. Bldg. 40 Years P.D.L. sheet 112B El. (-) 45'6" Zone A18 Flood Level Elev: Above Flood Level: Yes Sutnergence tin
- Documentation
References:
Notes: This component must function in a radiation (only) environment. Il2-B 11-1-80
. ~ . . .
SCEWS Ns. , 112-B I TER No. 68 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCW sheet. None II) Response to SER con: erns. (RPN, R QM, A) This equipment will be replaced with fully qualified devices. I III) Response to TER concerns. O Same as II. ! IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
^^-"
lO WARY SEIIT NO. Il2B SCIW SEEET NO. l 'DATE: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION O DISCREPANT EQUIPMENT StBMARY MILLSTONE UNIT 2 EQUIPMENT: STEM MOUttrED LIMIT SWITCHES ZS-6080, 6084, 6088, 6092 Containment Air Recirculation Cooler Control Valve MANUFACTURER: National Acme Corporation (NAMCO) QUALIFICATION DISCREPANCY: These co:nponents lack documented qualification data. ( SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment provides contacts for control circuit input and position indication for containment isolation valvos that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will , receive an insignificant radiation dose prior ta its required control operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices Refer to G=neric Replacement Schedule 1.
O O _ O Facility: (1 stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EhuGATION WORK S!!EET Docket: 50-336 EQUIPMENT DESCRIPTION EfNIRONMENT DOCUME!ITATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. Primary Makeup See summary i System: r perating Continuous 2S-7311 sheet ll3B Plant ID No.: Time Component: , , Temperature See summary Limit switch goF) 112 F A sheet 113B Manufacture: 11AMCO Pressure See summary (PSIA) sheet 113B 0.6 PSIG A ,Il Model Number: Relative See summary Humidity (%) sheet 113B 100 A Function: Position ind. ,
& valve control Chemical See summary
, Spray sheet 113B Accuracy: N/A
^ "^
Quench
- mk Radiation
- Service. makeup See suirnary 4 water entmt. isolat.an 1.94x10 'R C,L sheet 113B valve Location
- Aux. Bldg. Ag .g See summary
- ars L- sheet ll3B El. (-) 5 ' 0" Zone A18 Flood Level Elev: Above Flood Level: Yes Submergence un
- Documentation
References:
Notes: This component must function in a radiation (only) environment. t
- ll3-B 11-1-80
SCEWS Ns. 113-B TER No. ca Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Sutenary of new information on SCEW sheet. None -l II) Response to SER concerns. (RPN, R, QM, A) Ihis equipment will be replaced with fully qualified devices III) Response to TER concerns. Same as II. i f l l l IV) Propose; corrective action and schedule. Refer to corresponding equipment summary sheet. l V) Justification for continued operation. Refer to corresponding equipment summary sheet. O l
113B StattART EBEET NO. SCIW SEEET NO. 113B DATE: 8/21/81 EQUIPMENT ENVIRol0GNTAL QUALIFICATION DISCREPANT EQUIPMERT SIDMARY MILLSTONE UNIT 2 EQUIPMENT: STEM MOUNTED LIMIT SWITCHES ZS-7311 Quench Tank Makeup Water Conta nment Isolation Valve MANUFACTURER: National Acme Corporation (NAMCO) QUALIFICATION DISCREPANCY: These components lack documented qualification data. , SAFETY FUNCTION AND JUSTIFICATION l O( FoR CONT 1NuED orERAT1oN:
- This equipment provides contacts for control circuit input and position indication i for containment icolation valve ths.t function to mitigate a LOCA. It is located outside the containment and is subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will receive an insignificant radiation dose prior to its required control operation.
Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices Refer to Generic Replacement Schedule 1. 1 i O
- - - - -- , , - - _, ._, e-_-- - . - _ . , , , p -o-,,-wa s- ,.n ---.m- e- - .,e -------.,-n- - , ,
e
Facility: Alstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EV,wuATION WORK SIIEET Dockc*. 50-336 EQUIPMENT Dr.SCRIPTIOPJ ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING
~
METilOD ITEMS , Parameter Spec. Qual. Spec. Qual. g See summary system: 2 Operating Continuous sheet 116B Plant ID No.: ZS-7312 Time Cornponent : Linit switch Temperature
- See summary
( F) sheet 116B 112 F A Manufacture: NAMCO pressure See summary (PSIA) sheet ll6B 0.6 PSIC A ,Il Model Number: SL3C Relative See summary Function: Position 100 A Indication & valve Chemical See summary control spray sheet 116B Accuracy: N/A NA NA . Ssrvice: N2 stop valve to Radiation See summary S.I. tanks sheet 116B ~ Incation: Aux. Bldg. Aging El. (-) 5'0" See summary Zone A17 40 Yea rs P.D.L. sheet 116B Flood Level Elev: Above Flood Level: Yes lSulunergence nn I
*Documer.*ation
References:
Notes: This component must function in a radiation i (only) environment. ll6-B 11-1-80
SCEWS N2. 116-B TER No. 6R Date: 8/21/81 O EQUIPMENT ENVIRONM GTAL QUALIFICATION SER/TEk REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None i II) Response to SER concerns. (RPN, R, QM, A) This equipment will be replaced with fully qualified devices,
- III) Response to TER concerns.
Same as II. l IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. , O
leB
SUMMARY
SEEET NO. Il6B SCEW SHEET NO. P{
- DATE: 8/21/81 EQUIPMENT ENVIROl3(ENTAL QUALIFICATION DISCRIPANT EQUIPMENT SIDMARY MILLSTONE UNIT 2 EQUIPMENT: STEM MOUNTED lit!IT SWITCHES ZS 7312 Nitr ogen stop valve to safety injection tanks MANUFACTURER: National Acme Corporation (NAMCO)
QUALIFICATION DISCREPANCY: These components lack documented qualification dati.. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment providea contacts for control circuit input and position indication for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will , receive an insignificant radiation dose prior to its required control operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, it will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. l
O O _ O Facility: .lstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EV,u.UATION WGRK SiiEET Docket: 50-336
, EQUIPftENT DESCRIPTION ENVIRON!tchr DOCUMENTATION Ilt'* QUAL. OUTSTANDING
~
METilOD ITEMS Parameter Spec. Qual. Spec. Qual. See summary System: Primary Drain Operating Continuous Plant ID No.. ZS-9016 Time Component: Temperature Limit switch (op) See summary J 2F A sheet 119B N,WCO Manufacture: Pressure See m m (PSIA) sheet 1191 0.6 PEIG A ,Il See summary Model Number: SL3C Relative j llumidity (%) sheet 119B 100 A Function: Position .. indication 6 valve Chemical spray See summary control Accuracy: y
' sheet 119B See summary Service. Radiation Primary drain sheet 119B tank discharge isol 1.94x10 6R C,L
] Location: Anx. Bldg. ^91"9 See summary 4 Yea rs P.D.L. El (-) 5'0" sheet 119B Zone A17 Flood Level Elev:
- Above Flood Level
- Yes Sulxnergence un
- Documentation
References:
Notes: This component must function in a radiation (only) environment. 119-B 11-1-80
SCEWS No. 119-B TER No. 68 Date: 8/21/81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 l I) Summary of rew information on SCEW sheet. l Nore II) Response to SER concerns. ) This equipment will be replaced with fully qualified devices. III) Response to TER concerns.
- Same as II.
(7) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet.
.O I
,.-~--e.. , - . . . ,w, ----,_.--,.--me- ,.y-,---.w . - - --~ - - < - , ,
stb 01ARY SEEIT NO. Il9B SCIW SEEIT NO. Il9B
*lDATE: 8/21/81
{V] EQUIPMENT ENVIROlOIENTAL QUALIFICATI05 DISCREPANT BQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT: STEM MOULT 1*ED LIMIT SWITCHES ZS-9016 Primary drain tank isolation valve MANUFACTURER: National Acme Corporation (NAMCO) . QUALIFICATION DISCREPANCY: These components lack documented qualification data. { SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment provides contacts for control circuit input and position indication for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will , receive an insignificant radiation dose prior to its recuired control operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, it will be replaced with ful.y qualified devices. Refer to Generic Replacement Schedule 1. O
O Facility: ilstone Nuclear Pr. Sta. O O Uritt 'No
. SYSTEM COMPONENT Eb dATION WORK SilEET Docket: 50-336 EQUIPMENT DESCRIPTION r:NVIRomtENT DOCUMEtJTATION REF* QUAL. OUTSTANDING METIIOD ITEMS Parameter Spec. Qual. Spec. Qual.
System: RCS Operating C, See summary
'inuous Plant ID No.. Time sheet 120B ZS-505 Component: Temperature See summary Limit switch pp) ggg 112 F A Manufacture: Pressure See summary (PSIA) sheet 120B 0.6 PSIG A ,Il Model Number: "
SL3C """"I Ilumidity(%) sheet 120B 100 A Function: Position indication & valve Chemical See summary control Spray Accuracy: N/A sheet 120B NA NA
. RCP Bleed . See summary Service: Radiation Off Isol. valv : sheet 120B 2.12x10 R C,L Aux. Bldg.
g tjog:5'0" A9in9 See summary Zone A18 sheet 120B 40 Years P.D.L. Flood I4 vel Elev: Above Flood Level: Yes Submergence NA NA NA NA NA NA un
- Documentation
References:
Notes: This component must function in a radiation (only) environment. 120-B 11-1-80
SCEWS No. 120-B 68 TER No. Date: 8/21/81 O EQUIPMENT DiVIRONMENTA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Sute.ary of new inf ormation on SCEW sheet,
,j i None II) Response to SER concerns. (RPN, R QM, A) This equipment will be replaced with fully qualified devices. III) Response to TER cor.; erns. Same as II.
!V) Proposed corrective action and schedule.
Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
StBetARY SIIIT NO. 120B SCIW SHIET NO. 120B I */DATE: 8/21/81 EQUIPMENT ENVIRol0 ENTAL QUALIFICATION DISCREPANT EQUIPMENT S130(ARY MILLSTONE IDIIT 2 STEM MOUNTED LIMIT SWITCHES ZS-505 EQUIPMENT: Reactor Coolant pump bleed off isolation valve MANUFACTURER: National Acme Corporation (NAMCO) QUALIFICATICh DISCREPANCY: These components lack documented qualification data. c( V SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: This equipment provides contacts for control circuit input and position indication for containment isolation valves that function to mitigate a LOCA. They are all located outside the containment and are subject only to a radiation environment resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefore, this equipment will , receive an insignificant radiation dose prior to its required control operation. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, it will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 1. O
-,w.,- . , , - - , - ,g,-,-g
, Fccility: O 1ston? Nuclear Pr. Sta. O' O Unit: Two SYSTEN COMPONENT E% JATION NORK SHEET j Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONM!'.r OD IN Parameter Spec. _I Qual. Spec. Qual. l System Containment Press. Operating Sequential i Plant ID No.: Time Continuous Continuous 1,2,3 Test i 'T-82 38,82 39 - ! Component: Pressure Temperature Simulta-l Transmitter (OF) Profiles neous ll2*F 28,31 A 1,3 Test ! Hanufacture: Fo xbo ro Pressure Simulta-I (PSIA) Profiles neous Model Number: 0.6 PSIG 28,31 1,3 Test l A,Il ! NEllGM-11Cl-L-C-F Simulta- ! Relative Hsseidity(%) Profiles neous 100% 28,31 A 1,3 Test . l Y nction: Wide range ~ 1 pressure indication " Chemical Simulta-l Spray Profi1e neous j Accuracy: 0.5% span NA 15 NA 1 Test i service: Post Radiation Sequential ! actident monitoring 2.22x10 6R 2.2 x 10 8R C 2 Test i i 6 ) Incation: Aux. Bldg. Aging See summar) I elev. (-)5'0" A17,A18 sheet 121B l 40 years P.D.L. 4 Flood Imvel Elev: Above Flood Imvel: Yes Sulmergence NA NA NA NA NA j i
- Doc e ntation
References:
Notes: j 1. Foxboro rest Report T3-1013
! 2. Foxboro Test Report T3-1068
- 3. Foxboro Test Report T3-6061 l
j - 121-B 11-1-80
SCEWS Ns. 121-B TER Ns. 74 Date: 8/21/81 O' EQUIPMENT ENVIRONMDITAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 L Docket No. 50-336 I) Summary of new infornation on SCEW sheet. None II) Response to SER concerns.(A) This equipment will be replaced with fully qualified devices i III) Response to TER concerns. O Same as 11. 1 IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. J
SUMMARY
SHEET NO. 121B SCEW SHEET NO. 121B DATE: 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 2 Containment Pressure Transmitter 9 PT-8238, 8239 EQUIPMENT: MANUFACTURER: Foxboro Model NE11GM-11Cl-L-C-F These components lack documented radiation and QUALIFICATION DISCREPANCY: time / temperature aging qualification. SAFETY FUNCTION AND JUSTIFICATION f- FOR CONTINUED OPERATION: (~3'j This equipment functions tc provide wide range pust accident indication of containment pressure.
' n to the present age of this equipment, and to the severity of the envitenmental est en this equipment in the as new condition, reasonable assurance is providea
. hat the equipment will perform its design function.
Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. ( \_/
- a. .. _. _ - . . . _ . . . . . , . _ .
4 i Fccilitys O listona Nuclear Pr. Sta. o o I Unit: 'hso SYSTEM COMPONENT Ei. UATION WORK SHEET ! Docket: 50-336 1 i . ENVIRONMENT DOCUMENTATION REF* QUAL. OtfrSTANDING EQUIPMENT DESCRIPTION ITEMS ME'IHOO Parameter Spec. Qual. Spec. Qual. ! System Simulta- { System Rad " nitoring Operatin9 Design neous i Plant ID No.: Z1RM8240/ Time Continuous Continuous (P.A.M.) 1.a) Test ' P,C - Z2RM8241/B,C Simulta-i Component: Coaxial cable Temperature i (op} neous ! Profile 20 Profile 39 A,D 1.a) Test Manufacture: Pressure Simulta-
- Rockbestos Co. (PSIA) neous
} Model Number: RSS 6-104 Note 1 Profile 39 A 1.a) Test Design Simulta-Relative neous Require-t Humidity (4) 100% ment 1.a) Test 100% Function: Rad monitoring l cable Chemical 1 4 Spray l kcuracy: Not required 8 NA NA NA NA NA Service: Low level signal Radiation , j circuits NA NA NA NA NA f Incation: Various areas Aging Plant outside containment Design Sequential a 40 Yrs. 40 Yrs. Life 1.c) Test Flood Imvel Elev:
- Above T**
- xx1 Invel: Yes Sulanergence
, - un 1 l
- Documentation
References:
Notes: 1. The pressure is less than 2PSIG for ,
- 1. Rockbestos report " Qualification of fIrewall III about 13 seconds. This is considered insign'ficant.
coaxial constructions dated January 18, 1978".
) a) Page 2, Par. IV c) Pa;e 2, Par. II I
i 122-B 11-1-80
SCEWS No.122-B 75 TER No. rh 8/21/81 (,)i Date: EQUIPMENT ENVIRONMENTAL QUALIFICATICN SER/TER REVIEW Millstone Unit 2 Docket No. 50-336
- 1) Summary of new information on SCEW sheet.
None II) Response to SER concerns. (A) Refer to description of surveillance and preventive maintenance program contained in body of submittal. V
-4 III) Response to TER concerns.
Qualified life is greater than or equal to the plant design life. The above referenced surveillance program vill periodically verify the aging analysis. IV) Proposed corrective action and schedule. Equipment will be incorporated into plant surveillance and preventive maintenance program. V) Justification for continued operation. Not applicable O
}
10 () g (D V Fccility: 11 stone Nuclear Pr. Sta. Unit: Two SYSTEM LN Eb EATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTIOh METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System Reactor Cooling Operating Intermitt- 4195 Note 2. 2.a) Sequential Plant ID No.: RC403,RC405 Time ant Cycles Fest Simulta-Ccamponent : Valve Ntor Temperature (OF) Profile Profile neous Operations 18 11 4 2.b) Test l l Manufactures Pressure SinAlta-Limi to rq ue (PSIA) Profile Profile D 2.c) nc<us l Model Number: Ope rator 19 11A Test S/N's 156210,156209,0rder Simultd-No. 363562 A Relative Humidity (%) neous Function: Pressure relief 100 100 1. 2.d) Test - isolation valve operators ' Chemical Simulta-Spray 2400 PPM neous
' Boron Note 1. F 2.e) Test Accuracy: Not required Service: Porv block valve Radiation Sequential 8 8 1.5 x 10 2.04x10 R K,L 2.f) Test Incation: Contait men t Agin9 100 hrs at Plant EL 38'6" 180 C Design Sequential 40 Yrs. (40 Yrs.) Life 2.9) Test Flood Level Elev:(--)14'4" Above Flood Level: Yes X Subnergence NA NA NA NA NA un
- Documentation
References:
Notes: 1. Table 1, IEEE STD 382, Page 12
- 1. Bechtel Technical Spec. 7604-M-22 % 2. Must operate intermittently during a TMI type 7604-E-40, 7604-E-11B event to block and unblock porv as required.
- 2. Limitorque Project Report 600456, June 7, 1974 to November 22, 1974 a) Page 25 b) Fig. 6 c) Fig. 5 d) Par. 3.4.2 l e) Par. 4.4.2 f) Par. 4. 3.
g) Par 3.1.1 1-C 11-1-80
SCEWS No. 1-C TER No. 70D () I Date: 8/21/81 EQUIPMENT DIVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new f nf ormation on SCEW sheet. None II) Response to SER concerns. (A) Refer to description of surveillante and preventive maintenance program contained in body of submittal.
) t III) Response to TER concerns. ,
Qualified life is greater than or equal to the plant design life. The above referenced surveillance program will periodically verify the aging analysis. IV) Proposed corrective action and schedule. i Equipment will be incorporated into plant surveillance sad preventive maintenance program. l V) Justification for continued operation. l Not applicable i
O Facility: 1ston2 Nuclear Pr. Sta. N 'V Unit: Two SYSTEM COMPONDrr E\ JATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OCTFSTANDING EQUIPMENT DESCRIPTION ITEMS MEDIOD Parameter Spec. Qual. Spec. Qual. [' System: Reactor Coolant Operating Plant ID No. Tizze PT-103 Ca ponent: Temperature Simulta-Pressure Transmitter ( F) Profile Profile neous 18 318*F D 1,34 Test Manufacture: Foxboro Pressure Simulta-(PSIA) Profile Profile neous Modal Number: EllGM 19 90 PSI D 1,34 Test l Relative Simulta-Humidity (%) Profile neous Function: Low range 100 100% 1.34 Test . pressurizer press. 'Oiemical See summary Spray 2400 PPM sheet 2C
' F Accuracy: + 0.5% B ron Service: Radiation See summary , 8.2x10 6R K sheet 2C i
l Incation: CTMT (-) 5' Aging See summary l rack C-140 C-5 40 yrs. P.D.L sheet 2C Flood Imvel Elev: -14 ' 4" Above Flood Level: das X Suhnergence NA NA NA NA NA E l eDocumentation
References:
Notes: PT-103 S/N 2602027
- l. Foxboro Test Raport Q-9-6005 2-C 11-1-80
SCEWS No. 2_c TER No. 76 Date: - 8/21/81 EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (CS, R-SEN, RPN) This equipment will be replaced with fully qualifiet: devices. III) Response to TER concerns. Same as II. Iv; Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Refer to corresponding equipment summary sheet. O
't
2c I smenar saEET no. 2C SCEW SHEET NO. l m . DATE: 8/21/81 i Iv) - EQUIPMENT ENVIRONMENTAL QUALIFICATION i i DISCREPANT EQUIPMENT SIDMARY l 1 MILLSTONE UNIT 2 l EQUIPMENT: Low Range Pressurizer Pressure Transmitters PT-103 Foxboro E-11GM MANUFACTURER: QUALIFICATION DISCREPANCY: This equipment lacks documented qualification data concerning resistance to chemical spray and radiation exposure. SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION: PT-103 provides signal input for the post accident monitoring, subcooling margin monitor. This component serves as post accident low range presurizer pressure monitor This equipment also functions to provide overpressure protection for the shutdown cooling system. The post accident subcooling margin monitor, will alarm a pressure input failure which indicates to the operator that this system should not be used for any safety related function. l The overpressure protection for the shutdown cooling system is provided for in the plant operating procedures and ensured through administrative controls. Wide range monitors are also available to provide operating personnel with pressurizer pressure indication for shutdown cooling system initiation. l l Due to the desirability of long term operability of this equipment and in conformance with existing license requireme ts it will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. O
+ -.
o Fccility: O 1ston3 Nuclear Pr. Sta.
*O ~U Unit Two SYSTEM COMPONENT E\ JATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OtfrSTANDING EQUIPMENT DESCRIPTION MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.
See summary Operating c ntinuous Sy:: tem s haS sheet SC Plant ID No. : TE11211A-D. Time T E122ilA-D , T E112C A-D , TE122CA-D ' e g nent: Connection Temperd ure Profile 16, See summary llead ( F) 18 D 1 sheet SC Manufacture Rosemount Pressure Prof 11e 16. (PSIA) 19 D 1 See summary Model Number: (TE11211C- sheet SC 104ADA 104AFC-1) Relative 100% D See summary Humidity (4) 1 sheet 5C Function: RCS loop temp. RTD Cable Termination ' Gemical 2400 ppm Spray boron F 1 See summary
' sheet SC Accuracy:
Service: Radiation 1.5 X 10 t See summary ' K 1 sheet SC Incation: CTMF C-5 Aging See summary 40 yrs. P.D.L. sheet SC Flood Level Clev: (-)14'4" N/A N/A N/A N/A N/A Above Flood Level: Yes > Sulmergence tan
- Documentation
References:
Notes:
- 1. 8-27-79 letter from J. Graham, Rosemount Engineering to R. K. McCarthy 5-C 11-1-80
SCEWS No. $-C TER Ns. 77 Date: 8/21/81 O' EQt'IPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (RPN, T. P, H, R, QM.) This equipment will be replaced with fully qualifled devices. III) Response to TER concerns. O Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet.
- 7) Justification for continued operation.
Refer to corresponding equipment summary sheet. O
, , _ . . - - . - - - .,,.,,..--._e, - ~ . - . . _ , . , _ , , _ . _ _ , . . . . . . . . , _ , , ~ . - - . _ _ _ . ~ , , , . . - . . ~ . , , , . - _ _ _ _ . - . . - , . . - - - . - . . . ,
SC StBelARY SEEET NO. SC SCEW SHEET NO.
^
- EQU'/ MENT ENVIRONMENTAL QUALIFICATION DISCREPANT F.QUIPMENT SUlt(ARY MILLSTONE UNIT 2 EQUIPMENT:
RCS loop temperature RTD connection heads TE-ll2CA-CD TE-112HA-HD TE-122CA-CD TE-122HA-HD AANUFACTURER: Rosemount QUALIFICATION DISCREPANCY: These components lack documented qualification data. N OF T These components pro' Je protection for the cable terminations of the referenced RTD's. Ti se RTD's provide control room indication of the monitored parameters and RPS input for the thermal margin / low pressure trip setpoint determinations. Reasonable assiirance that these components will provide the required protection is irovided by Reference 1 on system component evaluation work sheet. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices Refer to Generic Replacement Schedule 1. O
O o j Facility: ' 'Iston2 Nuclear Pr. Sta. o^ V SYSTEM COMPONENT E. JATION WORK SHEET
- Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT l EQUIPMENT DESCRIPTION ME*IHOD ITEMS l
{ EE Sil 454 Parameter Spec. Qual. Spec. Qual. l System. Aux. Feed Water Operating Sequential Plant ID No.: FT-5277 Time Continuous Continuous 1,2,3 Test 5278 Simulta-Component: Dif ferential Temperature Profile Profile neous pressure 'ransmitter (OF) 326*F 28,31 20A 1,3 Test Manufacttare: Fo boro Pressure Simulta-(PSIA) Profile neous Model Number: N E13Dil 1.8 PSIG 28,31 A 1,3 Test Relative Simultd-Humidity (%) Profile neous 100 28, 31 A 1,3 Test Function: Aux. feed
- flow indication 'Oienical Simulta-Spray Profile neous
' Test Accuracy: =0.5% NA 15 NA 1 Service: Radiation Sequential
' 2.2 x 10 8 R 2 Test Incation: Zone A-51 Aging See summary j' 40 yrs. P.D.L. sheet 8C Flood Ievel Elev: Above Flood Level: Yes Submergence un i
;
- Documentation
References:
Notes: j 1. Foxboro Test Report T3-1013
- 2. Foxboro Test Report T3-1068
- 3. Foxboro Test Report T3-6061 l
4 8-C 11-1-80 l
SCEWS Ns. g_c TER N2. ra Date: 8/21/81 O' EQUIPMENT ENVIRONMENTA1. QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new infornation on SCEW sheet. None II) Response to SER concerns.(QI, R, QT, A, T, QM) This equipment will be replaced with fully qualified. devices. III) Response to TER concerns. O Same as II. l IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. I l V) Justification for continued opera ?on. 1 I Refer to corresponding equipment sur ary sheet. O
StBetARY SHEET NO. 8C SCEW SHEET NO. t
' DATE: 8/21/81 EQUIPMENT ElWIBOMMENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDMARY MILLSTONE UN'/.T 2 EQUIPMENT: Differential pressure transmitterP for auxiliary feedwater flow indication FT-5277, 5278 MANUFACTURER: Foyboro Model NE-13DH QUALIFICATION DISCREPANCY:
These components lack documented radiation and time / temperature aging qualification. ( SAFETY FUNCTION AND JUSTIFICATION p FOR CONTINUED OPERATION: 'J These components provide indication of auxiliary feedwater flow. An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis of this equipment. Due to to present age of this equipment, and severity of the as new test, reasonable assurance is provided that the equipment will perform its function. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. e B 0
O Facility:
'Iston2 Nuclsar Pr. Sta.
tv
^ V-Unit: Two SYSTEM COMPONENT E. JATION WORK SHEET Docket: 50-336 e
ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME*1 HOD ITEMS EEQ Sil 450 452 Parameter Spec. Qual. Spec. Qual. Systems Main Steam Operating Sequent t al 1'lant ID No. : LT-1113B,C,D Time Continuous Continuous 4 1,2,3 rest LT-ll23B,C,D , Component: Differenttal Temperature Simulta-I pressure t ransmitter ( F) Profile Profile neous 18 28,31 D 1,3 Test Manufacture: Foxboro Pressure Simulta-l (PSIA) Profile Profile neous Model Number: 19 28,31 D 1,3 Test ( NE-13-DM-III-M2 Relative Simultd-Humidity (%) Profile neous Function: Steam genera- 100 28,31 1,3 Test . tor level ' Chemical Simulta-Spray 2400 PPM Profile neous Accuracy: 0.5% span Boron 15 F 1 Test Service: Radiation Sequential 8.2 x 106 R 2.2 x 10 8 R K 2 Test Incation: CTMT 14'6" C-5 Aging See summary 40 yrs. P.D.L. sheet 9C Flood Ievel Elev:(-)14'4" Above Flood Invel: Yes X Submergence NA NA NA NA NA un
- Documentation
References:
Notes:
- 1. Foxboro Test Report T3-1013 ,
- 2. Foxboro Test Report T3-1068
- 3. Foxboro Test Report T4-6061 4 MPII FSAR Table 7.5.2 9-C 11-1-80
a r.a . -- . ._ TER N3. 79 Date: 8/21/81 EQUIPMENT UVIRONh' ENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Respanse to SER concerns. (A) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. 1 IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. i V) Justification for continued operation. Refer to correspcnding equipment summary sheet. l O
..-- - .. . . - , - ~ . .. ..-..,-----.._.--..,___--,----_~._--,_.-,---_y . . . . - - . - ~ ~ - - . . _ _ _ . . . _ . . . . - - - . - - . _ , - -
9C SUlelARY SEEET NO. 9C SCEW SHEET NO. EQUIPMENT ENVIRO 10GNIAL QUALIFICATION DISCREPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 EQUIPMENT: Differential pressure transmitters for steam generator level monitoring. MANUFACTURER: Foxboro Model NE-13-DM-H1-M2 QUALIFICATION DISCREPANCY: These components lack documented radiation and time / temperature aging qualification. ( SAFETY FUNCTION AND JUSTIFICATION
/ FOR CONTINUED OPERATION:
This equipment provides input for a reactor trip on low steam generator level, control room indication of steam generator level and automatic initiation of auxiliary feedwater on a low steam generator level condition. Due to the present age of this equipment, and to the severity of the environmental test on this equipment in the as new condition, reasonable assurance is provided that the equipment will perform its design function. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. I i l i i O l l i I l
(3 r Ftcili9: 1ston3 Huciccr Pr. Stn. V^ Unit: '1%eo SYSTEM COMPONENT E\ JATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD IN EE SH 486 Parameter Spec. Qual. Spec. Qual. Systeer RPS Operating continuous continuous 1, 2 Simultaneou' Plant ID No.: Time Test PS-4597 A,B,C,D Component: Pressure Temperature 155 F Simultaneous switch ( F) 160" F Profile 1, 2 Test 22 Manufacture: Custom Pressure Simultaneous Component (PSIA) 0.5 PSIG 16.0 PSIA Profile 1, 2 Test Model Number: 22 CCS 604CR6-356S Relative 100% 100% Profile Simultaneou: Humidity (%) 22 1, 2 Test Function: Turbine trip
' Chemical Spray Accuracy:
N/A Service: Radiation N/A Incation: Zone T11 Aging See summary 40 Years P.D.L. sheet 14C Flood Imvel 5"ev: Above Flood Imvel: Yes Suinergence N/A N/A N/A N/A N/A N/A un
- Documentation
References:
Notes:
- 1. 10-13-80 letter from Theryn Eckstein, Custom Control Sencors, to R. K. McCarthy
- 2. Custom Component Switches, Inc. Test Report QTR604-01 14-C 11-1-80
SCEWS No. 14-C TER N3. 80 Date: 8/21/81 O EQUIPMENT DWIRONMLNTAL QUALIFICATION SER/TER REVIEW Millstoue Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. None II) Response to SER concerns. (A) This equipment will be replaced with fully qualified devices. III) Response to TER concerns. Same as II. IV) Proposed corrective action and schedule. Refer to corresponding equipment summary sheet. V) Justification for continued operation. Ref er to corresponding equipment summary sheet. O
munnnas emana av. 1C SCEW SEEET NO. [ DATE: 8/21/81 (! EQUIPMENT ENVIRONMENTAL QUALIFICATION O" DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 2 Pressure Switches PS-4597A, B, C, D EQUIPMENT: High pressure turbine - hydraulic fluid pressure , Custom Component Switches (CCS) MANUFACTURER: These components lack documented time / QUALIFICATION DISCREPANCY: tamperature aging qualification data. 1 SAFETY FUNCTION AND JUSTIFICATION l FOR CONTINUED OPERATION: . O Twe e =etree e=t- reectie# te c e e fluid pressure. re cter trie ' 1 er tersi e aFa eetic Due to the present age of thic equipment, and to the severity of the enviroamental test on this equipment in the as new condition, reasonable assurance is provided that the equipment will perform its design function. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices. Refer to Generic Replacement Schedule 2. (
- O
* - ;,7....._ . . . , . , . . . . , . , . . . .. . . . . . . . . . . .
j
Fccility 'Istona Nuclerr Pr. Sta. () ,] '} Two. SYSTEM COMPONENT E' JATION WORK SHEET Unit Docket: E6 '336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT MEDIOD ITEMS Parameter Sptc. Qual. Spec. Qual. Simulta-System: Radiation Monit. Operating , neous Time 2a Plant ID No.: Test RE 8240, 8241 Continuous Continuous 1 ~~ Simulta-Component: liigh ran3e Temperature neous r.'iiation detector (OF) Profile ,," 18 340*F D Test Manufacture: Pressure Simulta-General Atomic (PSIA) Profile n us 2a tadel Number: RD-23 19 , 70 PSIG D Test Simulta-Relatire n us Humidity (%) 2a Test 100% 100% D. . Function: Accident / post ~ accident radiation ' Chemical Simulta-monitoring Spray 2400 PPM 3000 PPM 2a neous
' Boron Peron F Test Accuracy: + 3%
Service: Radiation U Test anc 1.5 x 108 R 2.0 x 10 8R K Analysis Location: CTMT Aging 25 Teet and elev. 18'6" 40 Yrs. PDL Analysis
, 40 Yrs.
Flood Imvel Elev:(-)l4'4" Abe"- Flood Level Yes X Subnergence NA NA NA NA NA NA Mn (Documentation
References:
- 1. Millstone II FSAR Table 7.5.2
- 2. General .itemic Test Etipe r t , Class IE Tecting of Analog High Eage Cadiatian Mcnitor E-2 54-960. i)/.P.",X1 b) \PDE 4.
c)Pd 2u, Sectic, 4.1 .. 15-C d-21-81
~
l SCEWS N3. TER No. Date: 8/21/81 O EQUIPMENT ENVIRONMDITAL QUA1.IFICATION SER/TER REVIEW hillstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. Qt alification inf orcation contained in Gcncral Atonic Test Peport F-254-960,now included, which gompletes qualification. 1 i i II) Response to SER concerns (%I '\ ,* See I above. Refer to description of surveillance and preventive maintenance program contained in body of submit:.al. ( III) Response to TER concerns. I Same as II. > IV) Proposed corrective action and schedule. l Equipment will be incorporated into plant surveillance and preventive maintenance program. i i V) Justification for continued operation. Not applicable O
O O ^ Om Pcc111ty: Ictene Nuclear Pr. Sta. Unit: 'Iwo SYSTEM COMPONENT Et JATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING ~ EQUIPMENT DESCRIPTION ME'ntOD ITEMS Parameter Spec. Qual. Spec. Qual. _ Simulta-System: Post Accid. Monit. Operating neous Plant ID No.: LT-8242, Time Continuous Contiuuous 1 Test a 8243 Component: Level Trans- Temperature Simulta-mitter (OF) Profile neous 18 381*F D Test a Manufacture: GEM Pressure Simulta-(PSIA) Profile neous Model Number: 19 60 PSIG D Test a XM-548532-84-1500 Simulta-Function: Containment ~ 1 sump level indication ' Chemical Simulta-Spray 2400 PPM neous
' Boron ph=11.0 F Test a Accuracy:
Service: Post accident Radiation Sequential monitoring 1.5 x 10 8 R 2.0 x 10 8 ,K Test a Incation: CTMT Aging elev.(-)22'6"-(-)15'6" . 0 Yrs. 40 Yrs. PDL es a I Flood Level Elev:(-)14'4" "*"EI"I Above Flood Level: Yes Submergence 14' 4" 14' 4" a t
- Documentation
References:
Notes: a. This equxoment is purchasec on a risk release basis pending ccmple tion of vendor qualification testing and NUSCO review and acceptance of the final test reports. The target date for receipt of the vendor's final test report is 10-81. The qualification documentation references will be identified at that time. 16-C 8-21-81
SCEWS No. (p c TER No. 82 Date: 8/21/81 C)
't_s EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet.
SUBMERGENCE ADDRESSED II) Response to SER concerns. (QI, A, S) REFER TO CORRESPONDING SCEWS s III) Response to TER concerns. O SAME AS II IV) Proposed corrective action and schedule. REFER TO CORRESPONDING SCEWS V) Justification for continued operation. NOT APPLICABLE gs_s
O () O U Fccility: '.llctone Nuclear Pr. Sta. Unit: Two SYSTFM COMPONENT E..oUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDI?tG EQUIPMENT DESCRIPTION METHOD ' ITEMS Parameter Spec. Qual. Spec. Qual. PZR relief valve Simulta-Systems monitors Operating neous Plant ID No. : ZS200,201, Time Continuous Continuous 1 Test a 402,404 Component: Accelerometer Temperature Simulta-( F) Profile neous D Test a 16.18 Profile 41 1 Manufacture: Endevco Pressure Simulta-(PSIA) Profile neous Model Number: 2273A.420 16,19 Profile 42 D 1 Test a Simulta-Relative neous Humidity (%) a 100% 100% D 1 Test . Function: Pos t a c c . . 'e n t monitoring ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous
' Test a Accuracy: Boron Boron F 1 Service: Porv discharge Radiation Sequential line monitoring 1.5 x 10 R 2 x 108 R 8 K 1 Test a Incation: CTMT C-5 Aging Plant To Be Design Sequential 40 yrs. Determined Life 1 Test a,b Flood Imvel Elev:(-)l4'4" Above Flood Level: Yes X Submergence un
- Documentation
References:
Notes: a. This equipment is purchased on a risk release
- 1. Babcock & Wilcox, valve monitoring system. basis pending completion of vendor qualification testing test program 3-21-80. and NUSCO review and acceptance of the final reports.
The target date for receipt of the final test report is 10-81. The qualification documentation references will be identified at that time.
- b. The qualified life for this equipment will be determined in accordance with IEEE 323-1974 guidelines.
17-C 11 1 en
~ _
SCEWS No. 17-C TER No. 83 Date: 8/21/81 f EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. NONE II) Response to SER concerns. (QI, A) REFER TC CORRESPONDING SCEWS III) Response to TER concerns. O, SAME AS II l j IV) Proposed corrective action and schedule. REFER TO CORRESPONDING SCEWS V) Justification for continued operation. NCT APPLICABLE l l l l l l (")~\
\.
O Pccility: .llstona Nucle =.T Pr. Sta. O- O SYSTEM COMPONENT E%d,UATION WORK SHEE' Unit Two Docket 50-336 ENVIROtMENT DOCUME TION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEntOD ITEMS Parameter Spec. Qual. Spec. Qual. P7 '.t relief valve SI*"IE - System: 'aon it o rs Operating "" "" Plant ID Io.: ZS-200,201 Time Test a Continuous Continuous 1 , 402,404 Component: Cable Temperature Simulta-(OF) Profile neous 16,18 Profile 41 D 1 Test a Manufacture: Harline Pressure Simulta-Cable Endevco (PSIA) Profile neous Model Number: 1075:!6 16,19 Profile 42 D 1 Test a Simulta-Relative neous Humidity (%) 100% 100% D 1 Test a . Furn: tion: Post accident monitoritig ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous
' a Accuracy: Baron Boron F 1 Test Service: Porv discharge Radiation Sequential line monitoring 1.5 x 10 8R 2 x 108 R K 1 Test a Incation: CTMT C-3 Agin9 Plant To Be Design Sequential 40 yrs. Determined Life 1 Test ,b Flood Irvel Elev:(-)14 '4" Above Flood Level: Yes X Subne.rgence un .
.
- Documentation
References:
Notessa. This equipment is purchased on a risk release
- 1. Babcock 6 Wilcox, valve monitoring system. basis pending completion of vendor qualification testing test program 3-21-80. and NUSCO review and acceptance of the final test reports.
The target date f'r receipt of the final test report is 10-81. The qualification documentation references will be identified at that time.
- b. The qualified life for this equipment will be determined in accordance with IEEE 323-1974 guidelines.
1R_r 1*.t_on
SCEWS No. 18 C TER No. 84 Date: 8/21/81
] EQUIPMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new inf ormation on SCEW sheet.
NOSE II) Response to SER concerns. (QI, A) REPER TO CORRESPONDING SCEWS III) Response to TER concerns, t'/'h s_ SAME AS II IV) Proposed corrective action and schedule. REFER TO CORRESPONDING SCEWS V) Justification for continued operation. NOT APPLICABLE C\ \-)
Pccility: O 'llstona
. Nuclear Pr. Sta.
O- O Unit: '19 0 SYSTEM COMPONENT Es.JATION WORK SHEET Docket: 50-336 ) i EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING ME*IHOD ITEMS Parameter Spec. Qual. Spec. Qual. i PZR relief valve Syaitems monitors Operating Simulta-
"" "8 Plant ID No. : ZS-200,201 Time 402,404 Continuous Continuous 1 Test a Component: Preamplifier Temperature Simulta-(OF) Profile neous 16,18 Profile 41 D 1 Test a Manufacture : Unhol t z- Pressure Simulta-Dickie (PSIA) Profile neous Model Number: 22CA-ZTR 16,19 Profile 42 D 1 Test a Relative Simulta-Humidity (%) neous Function: Post accident 100% 100% D 1 Test a .
monitoring ' 3amical Simulta-Spray 2400 PPM 3J00 PPM neous Accuracy: ' 4 Boron Boron F 1 Test a Service: Porv discharge Radiation Sequential line monitoring 1,5 x lo 8 R 2 x 10 8 R K Test a 1 i Incation: CTMT C-5 Aging Plant To Be Design Sequential 40 yrs. Determined Life 1 Test a,b Flood IAvel Elev:(-)14'4" Above Flood Ievel: Yes X Submergence un
- Documentation
References:
Notes: a. This equipment is purchased on a risk release
- 1. Babcock 6 Wilcox, valve monitoring system, basis pending completion of vendor qualification testing and test program 3-21-80. NUSCO review and acceptance of the final test reports. The
- i. target date for receipt of the final test report is 10-81.
The qualification documentation references will be identi-fled at that time.
- b. The qualified life for this equipment will be determined in accordance with IEEE 323-1974 guidelines.
19-C 11-1 nn
SCEWS No. 19-C TER No. 85 Date: 8/21/81 V EQUITMENT ENVIRONMENTAL QUALIFICATION SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. NONE II) Response to SER concerns. (QI, A) REFER TO CORRESPONDING SCEWS III) Response to TER concerns. SAME AS 11 IV) Proposed corrective action and schedule. REFER TO CORRESPONDING SCEWS V) Justification for continued operation. i NOT APPLICABl.E r (v) l
O Facility: .llston2 Nuclear Pr. Sta. O_ O Unit Two SYSTEM COMPONENT EMEATION WORK SHEET Dociet: 50-336 t DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION MEntOD ITEMS Parameter Spec. Qual. Spec. Qual. l'4 R relief valve Simulta-Systems monitors Operating neous Plant ID No.: ZS-200,201 Time Continuous Continuous 1 Test a 402,404
'ilmulta-Component: Junction Box Temperature neous (Oy) Profile 16,18 Profile 41 D 1 Test a Manufacture: Hoffman Pressure Simulta-l (PSIA) Profile neous Model Number: 8064 CHNESS 16,19 Profile 42 D 1 Test a S itrui t a-Relative "CC"8 Humidity (%)
- Function: Post accident Simulta-m,tnitoring ' Chemical Spray 2400 PPM 3000 PPM neous
' Boron F 1 Test a Accuracy: Boron i Service: Porv discharge Radiation Sequential line monitoring 8 8 K 1 Test a 1.5 x 10 R 2 x 10 R Incation: CTMT C-5 Aging Plant To Be Design Sequential j l
40 yrs. Determined Life 1 Test a,b Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Sulanergence l
- Documentation
References:
Notes a. This equipment is purchased on a risk release
- 1. Babcock 6 Wilcox, valve monitoring system, basis pending completion of vendor qualification testing test program 3-21-80. and NUSCO review and acceptance of the final test reports.
The target date for receipt of the final test report is 10-81. The qualification documentation references will be identified at that time,
- b. The qualified life for this equipment will be deterNined in accordance with IEEE 323-1974 guidelines.
?p_c is e on
TER No. 86 Date: 8/21/81 EQUIPMD'T ENVIRONMENTAL QUALIFICATION p \' SER/TER REVIEW Millstone Unit 2 Docket No. 50-336 I) Summary of new information on SCEW sheet. NONE II) Response to SER concerns. (QI, A) REFER TO CORRESPONDING SCEWS g III) Response to TER ccr.cerns. 7-s) 'sms SAME AS 11 IV) Proposed corrective action and schedule. REFER TO CORRESPONDING SCEWS V) Justification for continued operation. NOT APPLICABLE
O O- O Facility: ..allstone Nuclear Pr. Sta. , Unit: Wo CYSTEM COMPONENT EVALUATION WOPX SHEET Docket: 50-336 DOCUMENTATIO REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RCS Operating ea ry Plant ID No. : PT-103-1 Time Compor.ent : Press. Xmt r. Temperature ( F) see summary profile 18 D sheet 1-D Manufacture: Pressure Fischer Port"r (PSIA) see summary profile 19 D sheet 1-D i Model Number: Relative 50EP1042BCSA Humidity (%) see summary 100% D sheet 1-D Function: Pressurizer pressure low range Chemical Spray 2400PPri see sunanary Accuracy:+ 0.5% Boron F cheer 1n Service: Radiation see suusnsry 8.2 x 10 6 R K sheet 1-D Iocation:CTNT b1dg. Aging ele. (-) 3'6" see summary fire zone C-5 40 yrs. P.D.L. sheet 1-D Flood Level Elev:(-)l4'4" . Above Flood Invel: na h Subnergence N/A h i N/A
- Documentation
References:
Notes: 1. S/N 7608A2003A3 1. 1-D 1/30/81
SmetARY SHEET NO. 1-D SCEW SHErr NO. 1-D 8-21-81 EQUIPMDTI ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUMARY MILLSTONE UNIT 2 Et%PMENT: Narrow Range Pressurizer Pressure Transmitter PT-103-1 MANUFACIURER: Fisher Porter SOEP Series QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: PT-103-1 function to provide a alarm a signal of the pressurizer pressure on the main control panel and provides pressure indication on the hot shutdown control panel. During plant shutde,in it provides a control signal to the shutdown cooling and safety injection tank isolation valves to open/close as part of a series of operations which bring the reactor from a hot standby to cold shutdown. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate *he transition from hot standby to cold shutdow . The current licensing basis for Millstone Unit No. 2 does not include the capability to achf::.ve cold shutdown using class IE equipment. Corrective measures could be taken, as required in .:he event of inoperability of "indicatior. only" devices.
O O O FEcility: . .lstonn Nucicar Pr. Sta. - SYSTEM COMPONENT EVM,UATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION FtNIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RCS Operating simultancots Plt;nt ID No.. LT-103 Time continuous test 1 Component: Level Xmtr. Temperature simultaneous pp) profile 18 318 F D profile 34 test Manufacture: Foxboro Pressure 1, (PSIA) simultaneous profile 19 90 PSIG D profile 34 test I. Model Number: E13DH Relative simultaneous Humidity (t) 100% 100% D profile 34 test Function: Pressurizer level 0-1001 Chemical Spray 2400 PPM see summary accuracy: + 0.5% Boron F sheet 2-D Service: Pressurizer Radiation see summary Icvel monitoring 8.2 x 106 R K sheet 2-D Incation:CINT b1dg. Aging ele.(-)3'6" fire zone C-5 see sununary 40 yrs. 40 yrs. P.D.L. sheet 2-D Flood Ievel Elev:(-)l4'4" Above Flood Level: YesX Submergence N/A N/A un $ Documentation
References:
Notes: 1. S/N 2648247
- 1. Foxboro Test Report Q9-6005
- 2. MP II FSAR Table 7.5.2.
2-D 1/30/81
StBSIARY SHEET NO. 2-D SCEW SHEET NO. 2-D 8-21-81 EQUIPMENT ENVIRotMENTAL QUALIFICATION DISCREPANI EQUIPMDIT SIDMARY MILLSTONE UNIT 2 EQUIPMENT: Pressurizer Level Transmitter LT-103 MANUTACTURER: Foxboro E13DH Series QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: LT-103 function to provide wide range indication of the pressurizer level on the main control panel, during plant startup and shutdown. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to f acilitate the transition f rom hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 l does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
indication only" devices.
l l l l O
b
%d /
L V Facility: a. .lstonn 13uclear Pr. Sta. Wo Unit SYSTEM COMPONENT EVALUATION FORK SHEET Docket: 50-336 EYNIItONMENT DOCUMENTATION REF* QUAL. OITTSTANDING EQUIPMENT DESCRIPTION MEntOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RCS Operating Plant ID No.:TE-109 Time sem continuous sheet 3-D Compone:it. : RTD Temperature ( F) see summary profile 18 D sheet 3-D , Manufacture: Rosemount l Pressure (PSIA) see summary profile 19 D sheet 3-D Model Number: Relative 104WC88AX ' Humidity (%) see summary 100% D sheet 3-D Function: Pressurizer vapor phase temp. Chemical Spray 2400 PPM see summary Accuracy: Boron F sheet 3-D S2rvice: Pressurizer Radiation see summary vapor temp. monitoring 8 sheet 3-D 1.5 x 10 R K Incation:C' INT b1dg. Aging ele. 38'6" ftre zone C-5 see sununary 40 yrs. P.D.L. sheet 3-D Flood Level Elev:(-)14'4" Above Flood Imvel: Yes X Subnergence N/A N/A un CDocumentation
References:
Notes: 1. S/N 75006 1. 3-D 1/30/81
SG MARY SEEET P0. 3-D SCEW SHEET NO. 3-D R-21-8) EQUIPMENT ENVIRONMDrTAL QUALIFICATION DISCREPANT SQUIPiGNT SUltWLW MILLSTCNE UNIT 2 EQUIPMENI: Pressurizer Vapor Phase Temp. Element TE-109 MANUFACTURER: Rosemount 104 Series QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COWOSENT ENVIRONMENTALLY: TE-109 function to provide temperature g indication of the steam phase in the pressurizer on the main control panel. O This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be ta' ten, as required in the event of inoperability of
" indication only" devices.
l I O l
f I ( Q V y Facility: h_.lstone Nuclear Pr. Sta. . Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME'IHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RCS Operatin9 see sumary Plant ID No.:TE-115 Time continuous sheet 4-D Component: RTD Temperature (op) see sumary profile 18 D sheet 4-D Manufacture: Rosemount Pressure (PSIA) see sumary profile 18 D sheet 4-D lbdel Number: 104ADA Relative Humidity (%) see summag Functions RCS loop #1 1007. D sheet 4-D cold leg temp. Chemical spray 2400 PPM see sumary Accuracy: Boron F sheet 4-D S:rvice:RCS loop cold leg Radiation see summary 1.5 x 10 8R K sheet 4-D Incation:CINT b1dg. Aging ele. (-) 3'6" fire zone C-5 see summary 40 yrs. P.D.L. sheet 4-D Flood Level Elev: (-)l4'4" Above Flood IAvel: Yes X Sulnergence N/A N/A un l
- Documentation
References:
Notes:
- 1. 1. S/N 75298 see 5-C 4-D 1/30/81
StBetARY SHEET NO. 4-D SCIW SHEET NO. 4-D O =au1rxtuT ==v1=o' tsTit ouittricirio" DISCREPANT EQUlPtGNT SUtelARY MILLSTONE UNIT 2 EQUIPMENT: RCS Loop 1B Cold Leg Temp. Element TE-115 MANUFACTURER: Rosemount 204 Series QUALIFICATION DISCREPANCT: This component lacks doctamented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFTING A COMPONENT ENVIRONMENTALLY: TE-ll5 function to provide "B" cold leg ( temperature signal to a wide range temperature recorder on the main control panel N and provides temperature indication on the hot shutdown control panel. During plant shutdown it provides a control signal to the pressurizer relief (solenoid operated) isolation valve for overpressure protection when the shutdown cooling system is initiated. The overpressure protection for the shutdown cooling system is provided for in the plant operating procedures and ensured through administrative controls. Wide range monitors are also available to provide operating personnel with pressurizer pressure indication for shutdown cooling system initiation. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 dces not include the capability to achieve cold shutdown using class lE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O l
l Fccility: O). .ston2 Nuclear Pr. Sto. O o SYSTEM COMPONENT EVALUATION WORK SHEET Unit Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual. 1
- l System
- RCS Operatin9 see suminary Plant ID No.: TE-125 Time continuous sheet 5-D Cossponent : RTD Temperature i
(op) see sununary profile 18 D sheet 5-D i ! Manufacture: Rosemount Pressure j (PSIA) see summary " profile 18 D sheet 5-D Model Number: 104ADA Relative see siennary Humidity (%) sheet 5-D 100% D Function:RCS loop #2 cold lee temp. Chemical spray 2400 PPM see sununary Accuracy: Boron F sheet 5-D i
' Ssrvice:RCS loop cold leg . Radiation ,_ ! 1.5 x 108 R K sheet 5-D Incation:CTMT b1dg. Aging ele. (-) 3'6" fire zone C-5 see summary sheet 5-D i 40 yrs. P.D.L.
Flood Invel Elev:(-)l4'4", j Above Flood Ievel: YesX Submergence N/A N/A un 8 Documentation
References:
Notes:
- 1. 1. S/N A7764 5-D 1/30/81
SmeUEr SEEET E0. 5-D ) l l 3CIW SHEET NO. 5-D
~
EQUIPMENI ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUlttAIT j HILLSTONE UNIT 2 EQUIPMENT: RCS Loop 2A Cold Leg Temp. Element TE-125 FANUFACI1TRER: Rosemount 104 Series QUALIFICATION DISCREPAFCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: TE-125 function to provide "A" cold leg temperature signal to a vide range temperature recorder on the main control panel and provides temperature indication on the hot shutdown control panel. During pla t shutdown it provides a control signal to the pressurizer relief (solenoid operated) isolation valve for overpressure protection when the shutdown cooling system is initiated. The overpressure protection for the shutdown cooling system is provided for in the plant operating procedures and ensured through administrative controls. Wide range monitors are also available to provide operating personnel with pressurizer pressure indication for shutdown cooling system citiation. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of l " indication only" devices. l t O l l l
Facility: O .lstone Nuclear Pr. Sta. O- O . Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME'INOD ITEMS Parameter Spec. Qual. Spec. Qual. Sy' ~ CVCS operating nt ID No.: FT-212 Time continuous e Component: Flow Xmtr. Temperature ( F) see sunmaary 108CT 1 sheet 6-D Manufacture: Foxboro ~ Pressure (PSIA) see simmanry 0.5 psig i sheet 6-D Model Number:E-13DH Relative see sununary Humidity (%) Function: Charging pumps 100% sheet 6-D flow Chemical Spray see sunungry Accuracy: 1 0.5% N/A N/A sheet 6-D , Service: Charging pump Radiation P-18A,B,C see sununary 2.0 x 10 8R 2 sheet 6-D Incation: Aux. b1dg. Aging ele. . (-) 25 ' 6" see sununary , fire zone A-19 40 yrs. sheet 6-D Flood Level Elev: Above Flood IArvel: Yes Sutunergence un N/A N/A CDocuanentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N
- 2. W.G.C. to H.R. Denton (NRC) dated 12/31/79 6-D 1/30/81
o SmetARY SEEET NO. 6-D SCEW SHEET NO. 6-D EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMEFT SUlttARY HILLSTONE UNIT 2 EQUIPMENT: Charging Pump Flow FT-212 MANUFACTURER: Foxboro E13DH QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: FT-212 function to provide flow indication of the charging pump discharge header on the main control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
.)
Fccility: O F. .lstons Nuclear Pr. Sta. o- o
- Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS
, Parameter Spec. Qual. Spec. Qual. System: CVCS Operating Plant ID No.: PT-225 Time continuous hee Component: Press. Xmtr. Temperature ( F) see sumary 108 F 1 sheet 7-D Manufacture: CE Pressure (PSIA) see sumary 0.5 psig 1 sheet 7-D I Model Number: MAC 551 Relative Humidity (%) see sumag i Function: Volume control 100% sheet 7-D tank preis. Chemical spray see sumary Accuracy: N/A N/A sheet 7-D Service: Volume control Radiation tank T-5 0 see sumary 2.0 x 10 R 2 sheet 7-D Incation: Aux. bldg. Aging ele . (--) 25 ' 6" see sumary 1 ire zone A-19 40 yrs. sheet 7-D i Flood Level Elev: - Above Flood Level: Yes Submergence un N/A
- Documentation
References:
Notes: I
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 24209
- 2. W.G.C. to H.R. Denton (NRC) dated 12/31/79 7-D 1/30/81
i SCEW SHEET NO. 7-D H-21-81 EQUlPMENT ENVIRONMENTAL QUALIFICATION O DISCREPANT EQUIPMDIT SUMARY MILLSTONE UNIT 2 EQUIPMDrr: Volume Control Tank Pressure FT-225 MANUFACTURER: G.E. MAC-551 QUALIFICATION DISCREPANCY: This component lacks documented qualification data, i 1 FUNCTION AND JUSTIFICATION FOR NOT PT-225 function to provide pressure QUALIFYING A COMPONENT ENVIRONMENTALLY: indication of the volume control tank on the main control panel. l This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from het standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of I
" indication only" devices.
l O
- O istone Nuclear Pr. Sta.
O- O Facility: I . SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OLTTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS j Parameter Spec. Qual. Spec. Qual. System: CVCS operating Time see suman Plant ID No. : LT-226 continuous sheet 8-D Component: Level Xmtr. Temperature ( F) see sumary 108 F 1 sheet 8-D Manufacture: CE Pressure (PSIA) See sumary 0.5 psig i sheet 8-D i > Model Number: Relative see sumary MAC-555111BCAA-3ABA Humidity (%) sheet 8-D 100% Function: Volume control tank level monitoring Chemical Spray see sununary Accuracy: N/A N/A sheet 8-D Service: Volume control Radiation tank T-5 8 2.0 x 10 R 2 sheet 8-D Iocation: Aux. b1dg. Aging ele . (-) 25 ' 6" see sumary fire zone A-19 40 yrs. sheet 8-D Flood Level Elev: Above Flood Level: Yes Submergence N/A N/A un
- Documentation
References:
_ Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N BH0822-14055
- 2. W.C.C. to H.R. Denton (NRC) dated 12/31/79 i
8-D 1/30/81
Sl39tAEY SHEET HO. 8-D SCEW SHEET NO. 8-D N 8-21-81 EQUIPMENT ENVIROl0 ENTAL QUALIFICATION DISCREPANI EQUIPMENT SUMARY MILLSTONE UNIT 2 EQUIPMENT: Velume Control Tank Level LT-226 MANUFACTURER: G.E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: LT-226 function to provide level indication of the volume control tank (VCT) on the main control panel and provides a control signal to the makeup control for make up to the VCT to maintain the proper level. Manual valve line up and manual start of the boric acid pumps also allows the operating personnel with makeup control for manual make up to the VCT to maintain the proper level. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
( Facilitf) .1 stone Nuclear Pr. Sta. SYSTEM COMPONENT %pALUATION WORK SHEET '- Unit Two Docket: 50-336 s' REF* QUAL. OUTSTANDING ENVIRONMENT DOCUMENTATI METHOD ITEMS EQUIPMENT DESCRIPTION
- Parameter Spec. Qu. 1. Spec. Qual. _
Sal ety injection Operating see summacy System: System 4 plant ID No.: PT-302X,Y Time sheet 9-D continuous Component: Press. Xmtr. Temperature see summary ( F) g 1 sheet 9-D 108 F Manufacture: CE Pressure see summary (PSIA) 1 sheet 9-D 0.5 psig Model Number: MAC-551 Relative see suarnary Humidity (%) sheet 9-D 100% Punction: LPSI Pump 1 & 2 header press. Chemical see summary Spray N/A sheet 9-D Accuracy: + 0.5% N/A Service:LPSI pump 1 & 2 Radiation see summary 7 2 sheet 9-D 1.0 x 10 R Location: Aux. b1dg. Aging see summary ele . (-) 45 ' 6" sheet 9-D fire zone A-2 40 yrs. Flood Level Elev: Above Flood Level: Yes Submergence N/A N/A Notes:
- Document &* ion
References:
- 1. S/N 29465-PT-302X
- 1. MP-2 FSAk Table 5-7 (Amendment 33) 2. S/N 29466-PT-102Y
- 2. W.G.C. to li.R. Denton (NRC) dated 12/31/79 9-D 1/30/81
Stas 4ARY SHErf 30. 9-D SCEW SHEET NO. 9-D E-21-81 O. EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUtttARY MILLSTONE UNIT 2 EQUIPMENT: LPSI Pump Discharge Press. PT-302X,Y MANUFACTURER: G.E. MAC-551 QUALIFICATION DISCREPANCY: These components 1sek documented qualification data. FUNCIION AND JUSTIFICATION FOR NOT PT-302X & Y function to provide QUALITYING A COMPONENT ENVIRONMENTALLY: dise rge pressure indication of each (P-42A & B) LPSI pump on the main control This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
, 4m /~h
'~ -
FacilithI .lstone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336
- ~ ~
ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHCL ITEMS Parameter Spec. Qual. Spec. Qual. Shutdown Cooling System: System Operating Plant ID No.: FT-306 Time see summary continuous sheet 10-D Component: Flow Xtmr. Temperature PF) see summary 108 F 1 sheet 10-D Manufacture: GE Pressure j (PSIA) see summary
- 0.5 psig 1 sheet 10-D s
Model Number: Model 555 Relative ilumidity (%) see summary ' Function: Shutdown 100% sheet 10-D cooling flow monitoring Chemir *! Spray see summary
! Accuracy:1 2% N/A N/A sheet 10-D Service: Shutdown htr. Radiation see summary exch. flow /LPSI flow 8 sheet 10-D 2.0 x 10 R 2 Location: Aux. b1dg. Aging cle.(-)25'6" see summary fire zone A-19 40 yrs. sheet 10-D Flood Level Elev. -
Above Flood Level: Yes submergence N/A N/A un
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 14061
- 2. W.G.C. To H.R. Denton (NRC) dated 12/31/79 10-D 1/30/81
SIBGUKY SHEET NO. 10-D SCEW SHEET NO. 10-D 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION
?
DISCREPANT EQUIPMDIT SUtetARY MILLSTONE UNIT 2 EQUIPMENT: Shutdown Cooling Flow IT-306 MANUFACTURER: G .E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT O ou^ttr"o ^ co"rost"' '"v'"o""'"'^"': -3o6 '""cti = t er vide - *"dic ti " of the shutdown cooling flow on the main control panel and provides a control
; signal to the shutdown cooling bypass throttle valve to control the rate of flow for shutdown cooling. Manual control of the shutdown cooling bypass valve also allows the operating personnel with control.
This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
~ __i 'lictone Nuclear l'r. Sta. - [
.,UATION WORK SHEET \-
Unit: TW SYSTEM COMPONENT Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING , EQUIPHENT DESCRIPTION METif0D ITEMS Parameter Spec. Qual. Spec. Qual. Safety injection System: System Operating Plant ID No. Time see sununary C "EI""""" sheet 11-D FT- 312, 322, 3 32,342 Component: Flow Xntr. Temperature 108 F 1 see summan sheet 11-D Manufacture: CE Pressure (PSIA) see summary 0.5 psig 1 sheet 11-D Model Number: Model 555 Relative 11umidity (%) see summary 100% sheet 11-D Function:LPSI flow monitoring Chemical Spray see sunnary Accuracy: + 0.5% N/A N/A sheet 11-D Service: LPSI flow to Radiation RCS loop 1,2,3 & 4 see summa n 2.0 x 10 8 R 2 sheet 11-D Location: Aux. b1dg. Aging ele.(-)25'6" see summary fire zone A-19 40 yrs. sheet 11-D Flood Level Elev: Above Flood Level: Yes Sutunergence no N/A N/A
' Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 ( Amendment 33) 1. S/N 24237-FT-312
- 2. W.G.C. to H.R. Denton (NRC) dated 12/31/79 2. S/N 24238-FT-322
- 3. S/N 24239-FT-332 4 S/N 24240-FT-342 11-D 1/30/81
S13 MARY SHEET NO. 11-D SCEW SHEET NO. ll-D C-21-81 O EQUIPMEKr ENVIRONMENTAL QUALIFICATION TISCREPANT EQUlPMDIT SUIMARY MILLSTONE UNIT 2 EQUIPMENI: LPSI Pump Discharge Flow FT-312,322,332,342 MANUFACTURER: G.E. MAC-555 QUALIFICATION DISCREPANCY: These components lack documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT
, QUALIFYING A COMPOSENT ENVIRONMENTALLY: These components furetion to provide flow indication of LPSI puiaps flow to the RCS loops on the main control panel.
O This equipment is required to fenction after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
< r acility b 'lstone Nuclear Pr. Sta.
. k/ '
i Unit: "Nce SYSTEM COMPONENT E.aLUATTON WORK SHEEl Docket: 50-336 j EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Operating Plant ID No.: TE-351X,Y Time see summary continuous sheet 12-D t Component : RTD Temperature ( F) see sununary 108 F 1 sheet 12-D Ma:auf acture : Rosemount Pressure (PSIA) See sununary 0.4 psig 1 sheet 12-D Model Number: 108MB42BB Relative Humidity (%) See summaryg Function: Shutdown cooling 100% sheet 12-D l temp. saonitoring Chemical Spray
,,, ,,,,,,7y
- Accuracy
N/A N/A sheet 12-D 4 Sirvice: Shutdown Radiation cooling system ** *'""""#7 1.0 x 10 6R 2 sheet 12-D l Incation: Aux. b1dg. Aging
- ele . (-) 25 ' 6" i fire zone A-9 see susunary 40 yrs. sheet 12-D j Flood Level Elev
Above Flood Invel: Yes Suhnergence j m N/A N/A , t .4 ,
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 3003-TE-351X
- 2. W.G.C. to H.R. Denton (NRC) dated 12/31/79 2. S/N 3004-TE-351Y 12-D 1/30/8L
SIDMARY SHEET NO. 12-D sczw s==zt ao- 12-o O ~ ~' EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMDIT UPetARY MILLSTONE UNIT 2 EQUIPMENT: Shutdown Cooling Temperature TE-351X,Y MANUFACTURER: Rosemount 180 Series QUALIrlCATION DISCREPANCY: These components lack documented qualification data. FUNCTION AND JJSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: TE-351X & Y function to provide 9 temperature indication of the shutdown cooling flow on the main control panel. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of "indi:ation only" devices. O
Facility: ' stone Nuclear Pr. Sta. Unit: Two SYSTEM COMPONENT EVA sATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EtNIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING - METHOD ITEMS Parameter Spec. Qual. Spec. Qual.
'lystem: Main Steam System Lperating Plant ID No.- SI-4194A Time see sumary continuous sheet 13-D Component: Vert. Indicator Temperature
( F) see summary , profile 22 D sheet 13-D Manufacture: CE Pressure (PSIA) see sumary 0.5 psig D sheet 13-D Model Number: Model 180 Relative Humidity (%) see sumary Fur.ction :Stm. gen. aux. 100% D sheet 13-D Iced pump turbine chemical upeed indicator Spray see sumary Act.uracy: + 1.5% FS N/A N/A sheet 13-D Service:Stm. gen. aux. Radiation feed pump H-21 see seg N/A N/A sheet 13-D . Incstion: Turbine bldg. Aging ele. 14'6" fire zone T-10 see sumary 40 yrs. P.D.L. sheet 13-D Flood Level Elev
- Above Flood Level: Yes Subnergence
~
m N/A N/A
- Documentation
References:
Notes:
- 1. S/N no
; 13-D 1/30/8I.
St391AK! SEEET NO. 13-D SCEW SHEET NO. 13-D 8-21-FI EQU1FMENT ENVIR0tetENTAL QUALIFICATION DISCREPANT EQU1FMDIT SUMtARY MILLSTONE UNIT 2 EQUIPMENT: Steam Generator Aux. Feedwater Pump (P-4) Turbine Speed SI-4194A MANUFACTURER: G.E. 180 Series QUALIFICATION DISCREPANCY: This component lacks documented qualificatina data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: SI-4194A function to provide speed indication of tha steam generator aux. feedwater pump turbine on the main O control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective ceasures could be taken, as required in the event of inoperability of
" indication only" devices.
O
O lstone Nuclear pr. Sta. r A o V Facilit y : Unit: Two SYSTEM WONENT EV u ATION WORK SHEET Docket 50-336
~
ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter spec. Qual. Spec. Qual. System:Feedwater System Operating see sumary Plant ID No.: PT-5281 Time sheet 14-D continuous Component: Tress. Xmtr. Temperature ( F) see summary profile 22 D sheet 14-D Manufacture- GE Pressure (PSIA) see summary 0.5 psig D sheet 14-D hodel Number: Model 551 Relative Humidity (%) See summary I Functim: Aux. feed pump 100% D sheet 14-D P-9B disch. hdr. press. Chemical Spray see sununary Accuracy: 1 0.5% sheet 14-D 73 7 service: Aux f eed pump Radiation see summary P-9B sheet 14-D N/A N/A foc tion: Turbine bldg. Aging ele.14'6" fire zone T-10 see summary 40 yrs. P.D.L. sheet 14-D Flood Ievel Elev: Above Flood Level: Yes Sulznergence
, N/A N/A 8 Documentation
References:
Notes:
- 1. S/N 29475 14 -D 1/30/81
StBetAIT SEEET NO. 14-D SCEW SEEET NO. 14-D 8-21-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPMrr EQUIPMDIT SUlttAIY MILLSTONE UNIT 2 EQUIPMENI: Steam Generator Aux. Feedwater Pump (P-9B) Discharge Pressure PT-5281 MANUFACTURER: G.E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documnted qualification data. FUSCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: PT-5281 function to provide pressure indication of the steam generator aux, feedwater pump discharge pressure on the nain control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit Nc. 2 does not include the espability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
m f~h _) 1ston2 Nuclur Pr. Sta. t ,,/ Ftcility: SYSTEM COMPONENT EVALUATION WORK SHEET Unit: 'INo r,oc nu 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMEP.T DESCRIP110N METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System:Feedwater Syster Operating g Plant ID No.: LT-5282 Time cotitinuous sheet 15-D Component : Level Xmt r. Temperature (o p) see summary D sheet 15-D profile 22 Manufacture: CE Pressure (PSIA) see summary 0.5 psir, D sheet 15-D Model Number:Model 551 Relative I see summary Humidity (%) sheet 15-D 100% D Function: Condensate storao,e tank level Chen;ical ; monitoring Spray l see su:mnary Accuracy: N/A sheet 15-D N/A Service: Condensate Radiation ,e see seg storage tank N/A N/A sheet 15-D Incation: Turbine b1dg. Aging ele. 14'6" fire zone T-10 see summary 40 yrs. P.D.L. sheet 15-D Flood Level Elev: Above Flood Level: Yes Subnergence N/A N/A un CDocumentation
References:
Notes:
- 1. S/N 29445 15-0 1/30/8L
e,.. - - -+ St300E! SHEET NO. 15-D SCEW SHEET NO. 15-D EQUIPMENT ENVIR0t9 ENTAL QUALIFICATION DISCREPANI EQUIPMENT SIDOUEY MILLSTONE UNIT 2 EQUIPMENT: ';ondensate Storage Tank Level LT-5282 NANUFACTURER: G.E. MAC-551 QUAL'*FICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATTON FOR NOT LT-5282 function to provide a level QUALIFYING A COMPONENT ENVIRONMENTALLY: signal of the condensate storage tank to a recorder on the main control panel and n v provides level indication on the hot shutdown control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using cl. s IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" de rices.
('" ') Fccilit '^ 1stont Nuclear Pr. Sta. SYSTEM COMPONENT EV, JATION WORK SHEET Unit: ' inn Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION ME*I110D ITEMS Parameter Spec. Qual. Spec. Qual. System:Feedwater System Operating see summary Plant ID No.* PT-5234 Time continuous sheet 16-D { f Component : Press. Xmtr. Temperature ( F) see summary l profile 22 D sheet 16-D l Manufact'ere: GE Pressure f I (PSIA) see s e n sheet 16-D I 0.5 psig D l Model Number: Model 551 Relative see sumary I Huniidity (%) j 100% D sheet 16-D Function: Aux feed pump ' P 4 disch. hdr. press. Chemical Spray see summary Accuracy: + 0.5% N/A N/A sheet 16-D S;rvice: Aux. feed Radiation see sumary pump P-4 N/A N/A sheet 16-D Iocation: Turbine bldg. Aging ele. 14'6" fire zone T-10 see summary 40 yrs. P.D.L. sheet 16-D Flood Ievel Elev: . Above Flood Level: Ves Suhnergence N/A N/A un
- Documentation
References:
Notes:
- 1. S/N 29476 16-D 1/30/81
Status! SEEET NO. 16-D SCEW SEEET NO. 16-D 8 '!1-81 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPAln EQUIFIGHT SulGUEY MILLSTONE UNIT 2 EQUIPMENT: Steam Generator Aux. Feedwater Pump (P-4) Discharge Pressure PT-5284 MANUFACTURER: C.E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: PT-5284 function to provide pressure n v indication of the steam generator aux. feedvater pump discharge on the main control panel, n is equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
,o . . , . . . 11 1 or - fluc l. a t Pr. 6ta. ' j Unit- N* SYSTEM COMPONENT n JATTON WORK SHEET DOCke' t : E O ' 3 t's
- i. try t pcren:=;T !Y)CUMEt3TATION REF* QUAL. OUTSTANDING .
EK'IP"GT T3Ril'TI 9r; -' METHOD ITEMS j- i Qual. Spec. Qual. p.Pa r.mw . _p _ Snc . . i ' i cre- :. M tt*i ir 'ra *. ; ri 3 I """ """*U Plant It No.- PT- U84 Tine l L continuous sheet 17-D Component: Press. Xmtr. Temperature ( F) see summary profile 22 D sheet 17-D Manufacture. GE Pressure (PSIA) See summary 0.5 psig D sheet 17-D Model Number: Model 551 Helative Humidity (%) See summary Funciion: Aux. feedwater 1 100% D sheet 17-D pump P-9A disch. hdr. Chemical press ruonitoring Spray see summary Accuracy: 0.5% N/A N/A sheet 17-D Service: Aux, feed Radiation pump P-9A see summary N/A N/A sheet 17-D Iocation: Turbine b1dg. Aging ele. 14'6" ftre zone T-10 see summary 40 yrs. P.D.L. sheet 17-D Flood Level Elev: Above Flood Level: Yes Suhnergence gn N/A N/A 8 Documentation
References:
Notes:
- 1. S/N 29477 17-D 1/30/81
SUletARY SHEET NO. 17-D SCEW SHE*T. NO. 17-D 8-21-81 p) q EQUlPMENT ENVIRONMENTAL QUALIFICATION nlSCREPANT EQUIPMDIT SUMARY MILLSTONE UNIT 2 EQUIPMENT: Steam Generator Aux. Feedwater Pump (P-9A) Discharge Pressure PT-5289 MANUFACTURER: G. E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: PT-5289 function to provide pressure indication of the steam generator aux. feedwater pump discharge on the main control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
C\ O fT U 's/ V Facility: Millstone Nuclear Pt. Sta. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEE'I Docket: 50-336 , EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATIOt REF* QUAL. OtfrSTANDING l METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RBCCW System Operating Plcnt ID No.: LT-6001 Tiate see summan continuous sheet 18-D Component: level Xmtr. Temperature 4 (OF) See summary 302 F 1 sheet 18-D I Manufacture: Foxboro Pressure (PSIA) see summary 1.0 psig 1 shee_t 18-D Mode) Number: El lDM Relative Humidity (%) see summan runction:RBCCW surge tank 100% sheet 18-D level monitoring chemical Spray see summary
+
Accuracy: .,0.5% sheet 18-D N/A N/A S:rvice: RBCCW surge rank Radiation see summary 6 4.8 x 10 R K sheet 18-D Incation: Aux. bldg. Aging ele. 71'0" see summary fire zone (none) 40 yrs. sheet 18-D Flood Imvel Elev: Above Flood Level: Yes Sutnergence L , N/A N/A
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-8 (Amendment 33) 1. S/N 2727401 18-D 1/1ntet
St3 MARY SEEET NO. 18-D SCEW SHEET NO. 18-D 8-21-81 O EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUIMARY MILLSTONE UNIT 2 EQUIPMENT: RBCCW Surge Tank Level LT-6001 MANUFACTURER: Foxboro E-13DM QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: LT-6001 function to provide level indication of the RBCCW surge tank on the main control panel. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
O tO (ah O Fccility: .. .lstona Nuclear Pr. Sta. Unit: 'No SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 FQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTAICIMG FITitOD ITEMS Parameter Spec. Qual. Spec. Qual. System: RBCCW System Operating Time see suimnary PIEnt ID No.:rT-6034 continuous sheet 19-D Component : AP Ce11 Temperature ( F) see summary 2 1080F 1 sheet 19-D l Manufactures GE Pressure (PSIA) see summary l 0.4 psig 1 sheet 19-D Model Number: Re:lative Model $$5111BCAA3A9A Itumidity (s) see summary Function: RBCCW HX out.let 100% i sheet 19-D i hdr. flow monitoring Chemical j Spray see suinmary l Accuracy: i U.5% N/A N/A sheet 19-D o S:rvice:RUCCW HX. Radiation l see summary N/A N/A sheet 19-D W ation: Aux. bldg. Aging ele . ( -)25' 6" see sunsnary fire zone A-1B 40 yrs. sheet 19-D Flood Level Elev: Above Flood Imvel: Yes Sulunergence na
- Documentation
References:
Notes: j 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N CH1022-28185 19-D 1/30/8L
I l SGMARY SHEET E0. 19-D SCEW SHEET NO. 19-D 8-21-81 O EQUlFMEE ENVIRONMENTAL QUALIFICATION j DISCREPAM EQU1FMENT SmMARY MILLSTONE UNIT 2 I EQUIPMEhT: RBCCW lleat Exchanger "B" Outlet Flow FT-6034 MANUFACIVRER: G.E. MAC-555 QUALIFICATION DI'CREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: FT-6034 function to provide flow indica-tion of the RBCCW heat exchanger outlet on the main control panel. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 l does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
I O
m Facility 1 stone Nuclear Pr. Sta. Unit: Two SYSTEM CORPONENT EVAudATION WORK SHEET , Docket: 50-.336 ENVIRONMENT D')TMENTATION REF* QUAL. OUTSTANDIN EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. System: Ri1CCk' System Operating Plant ID No. FT-6035 Time see sumary continuous sheet 20-D Component: A P Cell Temperature gop) see summary sheet 20-D 1080F 1 Manuf ac t.urc : CE Pressure (PSIA) see summary 0.4 psig 1 sheet 20-D Model i4 umber: Fodel 555 Relative Humidity (t) see summan 100% sheet 20-D Function:RBCCW lti outlet hdr. flow monitoring Chemical Spray see sutunary Accuracy: + 0.5% N/A N/A sheet 20-D Ssrvice: RBCCW IN Radiation see summary N/A N/A sheet 20-D Iocation: Aux. bldg. Aging ele . (-) 25 ' 6" see summary fire zone A-1B 40 yrs. sheet 20-D Flood Level Elev: Above Flood Level: Yes Submergence m N/A N/A
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 28181 20-D 1/30/81
SW90EY SHEET NO. 20-D SCEW SHEET NO. 20-D
~
EQUIPMENT ENVIRONMDrIAL QUALIFICATION DISCREPANT EQUIPMENT SU) MARY MILLSTONE UNIT 2 EQUIPMENT: RBCCW Heat Exchanger "A" Outlet Flow FT-6035 MANUTACTURER: C.E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPOSENT ENVIRONMENTALLY: FT-6035 function to provide flow indica-tion of the RBCCW heat exchanger outlet on the main control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facili':ste the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O
Facility: allstone Nuclear Pr. Sta, N } Unit: 'No SYSTEM COMPONENT EVALUATION WORK SIIEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING [ ME'I110D ITEMS Parameter Spec. Qual. Spec. Qual. Shutdown cooling System: System Operating Plant ID No.. FT-6047 Time continuous * " Component: A P Ce11 sheet 21-D Temperature ( F) see summary 1080F 1 sheet 21-D Manufacture: GE Pressure (PSI A) 1 see summary 0.5 psig sheet 21-D Model Number: Model 555 aet' ative Humidity (%) see summary Ptutetion : Shutdown HY 100% shell side flow sheet 21-D chemical
;' monitoring Spray Accuracy: + 0.5% see summary N/A N/A sheet 21-D
! S:rvice: Shutdown HX Radiation exch. X23B 1.0 x 10 7R 2 see summary Incation: Aux. Bldg. sheet 21-D Aging ele . (-) 45 ' 6"
) fire zone A-3 see summary 40 yrs. sheet 21-D Flood Level Elev:
Above Flood Level: Yes Subnergence i _ un N/A N/A 4
- Documentation
References:
Notes.
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1* S/N 30280
- 2. W.G.C. to H.R. Denton (NRC) dated 12/31/79 i
1-D 1/30/8L
~
StatogY SEEET NO. 21-D SCEW SHEET NO. 21-D EQUIPMENT ENVIRONMENAL QUALIFICATION DISCREPAE EQUIPMDIT SUttDEY l MILLSTONE UNIT 2 EQU1FMENT: Shutdown Heat Exchanger (X-23B) Flow TT-6042 MANUFArTURER: G.E. MAC-555 QUALIFICATION DISCREPANCY: This component lacks documented qualification date. FUNCTION AND JUSTIFICATION FOR NOT ET-6042 function to provide flow indica-QUALIFYING A COMPONENI ENVIRONMENTALLY: tion of the shutdown heat exchanger statllside on the main control panel. This equipment is required to function after a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
O V
F&cility: O..Allston2 Nuclear Pr. Sta. O o s Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 a ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec Qual. _ Spec. Qual. Shutdown cooling System: System Operatin9 see summary Plant ID No.. F1- 6043 Tim sheet 22-D continuous Component: 4 P Cell Temperature (opy see summary 108 F 1 sheet 22-D Manufacture: GE Pressure (PSIA) see summary 0.5 psig 1 sheet 22-D i Model number: Model 555 Relative Humidity (%) see summary Pa. et. loo . Shutdown llX. 100% sheet 22-D 1 shell side flow Chemical toonitoring Spray see sununary Accuracy: 0.5% sheet 22-D N/A N/A S:rvice: Shutdown HX. Radiation see summary exch. X23A 7 sheet 22-D
.0 x 10 R 2 ;
Incatioa: Aux. bldg. Aging e le . (--) 4 5 ' 6" see summary fire zone A-2 40 yrs. sheet 22-D Flood Ievel Elev: - Above Flood Level: Yes Sutsnergenc un N/A N/A
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 06061
- 2. W.C.C. to H.R. renton (NRC) dated 12/31/79 ,
mM S 22-D 1/30/81
~
e SIB 9tARY SEEET NO. 22-D SCEW SHEET NO. 22-D 8-21-81 EQUlFMENT ENVIRONMENTAL QUALIFICATION DISCREPANI EQUIPMENT SIDE (ARY MILLSTONE UNIT 2 EQUIPMENT: Shutdown Heat Exchanger (X-23A) Flow FT-6043 MANUFACTURER: G.E. MAC-5%5 QUALIFICATION DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFTING A COMPONENT ENVIRONMENTALLY: FT-6043 function to provide flot, indica-tion of the shutdown heat exchanger she11 side on the main control panel. O This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
Facility: O 1 stone Nuclear Pr. Sta. O 1O SYSTEM COMPONENT EVau11ATION WORK SHEET T Unit: Two Docket: 50-D6 ENVIRONMENT l DOCUMr.NTATIO REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME1 HOD ITEMS . Parameter Spec. Qual. Spec. Qual. i
- System
- RBCCW Systeru operating Plant ID No.: Time TIL-6306,7,8 C "'I"" "" sheet 23-D
] , cnmponent: ".empera ture Pneumatic Xmtr. (0 1-) see st m ary 108 F 1 sheet !3-D ' I Manufacture: F.sxboro Pressure
- (PSI A) see susaary 0.4 psig I sheet 23-D
.i ' i Model Numtv'r:Model Relative Humidity (%) see summary 434-M sheet 23-D Function: RBCCW ht.. exch. 100% j l temp. monitoring ' Chemical spray see summary M aracy: 0.4 N/A N/A sheet 23-D Service: RBCt.:9 ht. exch. Radiation XiSC see sunman i1 N/A N/A sheet 23-D Incation: Aux. b1dg. . Ming i; ele. (-) 25 ' t>" see sununary j fire zone A-1B 40 yrs. sheet 23-D _ Plood Level Elev: Above Flood Level: Yes Sulmergence m I., A N/A 4
*Docuumentation 'leferences: Notes:
- 1. MP-2 FSAR Table 5-7 (Amendment 33) 1. S/N 2624850-TIC-6306
- 2. S/N 2624851-TIC-6307
- 3. S/N 2624852-TI?-6308 i
I 23-D 1/30/81
StBetARY SHIIT NO. 23-D SCEW SHEET NO. 23-D 8-21-81
. EQU1FMENT ENVIRONMENTAL QUALIFICAIl0N DISC 782 ANT EQUIPMENT SLM(ARY MILLSTONE UNIT 2 EQUIPMENT; RBCCW Heat Exchanger Temperature Monitor TIC-6306,7,8.
MANUFACTURER: Foxboro 43A Series QUALIFICATION DISCREPANCY: These components lack documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT QUALIFYING A COMPONENT ENVIRONMENTALLY: TIC-6306,7 6 8 function to provide tempe . .e control to the RBCCW heat exchanger outlet valves on a local O instrument rack. This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures cocid be taken, as required in the event of inoperability of "indicstion only" devices. l l l 1 9 l
r - ( I Fccilityi' *lstona Nucicar Pr. Sts, v b Unit: "No SYSTEM COMPONENT Et.JATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual. System:RBCCW System Operatin<; ,' see sunenary Plcnt ID No.: LT-6730 Time sheet 24-D continuous component: Xmtr. level Temperature ( F) see summary J 302 F 1 sheet 24-D Manufacture: Foxboto Pressure (PSIA) s e su m g 1.0 psig 1 sheet 24-D Moiel Number: E13DM Relative humidity (%) see sununary Fimetion:RBCCW surge tank 100% sheet 24-D l Jevel monitoring chemical spray Accuracy: _+ 0.5% seesummary{ sheet 24-D
, N/A N/A i
S tvice: RBCCW surge Radiation see summary tank T-3 sheet 24-D 4.8 x 10 6 R K Location Aux. b1dg. Aging ele. 71'0" fire zone see sunumary 40 yrs. sheet 24-D 1 Flood Level Elev: Above Flood Level: Yes Sutsmergence N/A
, N/A
- Documentation
References:
Notes:
- 1. MP-2 FSAR Table 5-2 (Amendment 33) 1. S/N 2727402 24-D 1/30/81
5t39003 SEEET NO. 24-u SCEW SHEET NO. 24-D 8-21-81 EQU1FMENT ENVIROISENTAL QUALIFICATION DISCREPANT EQUIPMENT SWJtAln MILLSTONE UNIT 2 EQUIPMENT: RBCCW Surge Tank Level LT-6730 MANUFACTURER: Foxboro E-13DM QUALIFICATIC 3 DISCREPANCY: This component lacks documented qualification data. FUNCTION AND JUSTIFICATION FOR NOT
, QUALIFYING A COMPONENT 11NVIRONMENTALLY: LT-6730 function to provide level indication of the RBCCW surge tank on the main control panel.
This equipment is required to function af ter a design basis event exclusively to provide indication to operations personnel to facilitate the transition from hot standby to cold shutdown. The current licensing basis for Millstone Unit No. 2 does not include the capability to achieve cold shutdown using class IE equipment. Corrective measures could be taken, as required in the event of inoperability of
" indication only" devices.
l
t Facility: O listona Nuclear Pr. Sta. nV n
%/
1 Unit Two SYSTEM COMPONENT Ev.aEATION WORK SHEET ,.
; Docket: 50-336 4'
- ENVIRONMEt(T DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS ,
Parameter Spec. Qual. Spec. Qual. 1 4 , 4 l System:Che . 6 Vol. Contl Operating sequential i Plant ID No.: CH 504 Time note 2 1.a) tests l note 1 200 cycles ) Component: Valve Temperature i motor operator ( F) Manufr.cture: Limitorque Pressure (PSIA) i Model Nuhder: perator Relative i S/N 134330 Humidity (%) i Function: Operatot for ! CH 504 chemical Accurecy:Not required i Service RWST water Radiation sequential l valve to charging ! pumps header B.32 x 10 5R 2.04x108R C,L 1.b) tests Incation: Aux. bldg. Aging l lant ] el.(-)?5'6" zone A-9 simulated design sequential , 40 yrs. 40 yrs. life 1.c) tests _ Flood I4 vel Elev: . Above Flood Level: Yes Suhnergence ] - 1 4
- Documentation
References:
Notes: 1. Valve is manually controlled and used in transit from
- 1. Limitorque Test Report B0003 11/13/74 to 1/23/75 hot standby to cold r butdown only.
a) Par 2.1.3 2. P & ID 25203-26017 FSAR 9.2.2.3 b) Par 2.3 3. Valve must function in a radiation (only) environment c) Par 5.0 t 25-D 1/30/8L i 4
DOCUMENT REFERENCE LIST SUPPLDIEhT ( ,, A. Bechtel Nuclear Staff Calculation 532-27-11867 Rev. 0: Computer Run x3022, 11/3/79. B. The Chemical solution consists of 3000 PPM Boron as Boric Acid in solution with 0.064 Molar Sodium Thiosulfate buffered with Sodium Hydroxide to a PH of between 9 and 10 at Room Temperature. C. NUSCO response to NUREG-0578-Section 2.1.6b, Attachment 2, Summa ry Sheets, W. G. Counsil to H. R. Genton, December 31, 1979. D. NUSCO memorandum C. J. Gladding to R. J. DeRosa GME-80-274 dated Februa ry 29, 1980. E. NUSCO memorandum C. J. Gladding to R. J. DeRosa GME-80-70.* dated May 16, 1980. F. NUSCO memorandum S. J. Weyland to R. J. DeRosa GME-80-643 dated May 1, 1980. G. H. The peak pressure is less than 1 psig for a duration of about 13 seconds. This is considered insignificant. I. NUSCO memorandum C. J. Gladding to R. J. DeRosa GME-80-863 dated July 7, 1980. J. K. NUSCO memorandum D. Miller to R. J. DeRosa, NEE-79-E-281 dated May 21, 1979. L. NUSCO memorandum H. W. Siegrist to R. J. DeRosa NEE-80-RA-496 dated September 8, 1960. M. NUSCO memorandum H. W. Siegrist to R. J. DeRosa NEE-80-RA-519 dated September 16, 1980. N. NUSCO memorandum Ralph Bates to R. J. DeRosa dated September 11, 1980. P. " Operating Time" specification information is not noted either because it was not originally specified or could not be readily found. In all cases the qualified operating time adequately covers the equipment requirement.
,)
1 i () MISCELLANEOUS ELECTRICAL DEVICES A list of miscellaucous electrical devices has been developed from a review of the plant wireway drawings. The installed items have been inspected by plant walk-through for the purpose of specific identification and observation of conditions which could possibly cause circuit failure under accident conditions (Reference 2). The types of equipment identified are: Ideal set screw connectors 3-M Scotch-Lok twist on type connectors General Electric type EB5 terminal blocks Compression and other type terminal blocks (unidentified) Safety switches Fuses Fuse Block Butt Splices Environmental qualification considerations regarding the above equipment are as follows: Ideal Set Screw Connectors These devices are used inside and outside the containment. They are qualified inside the containment as shown on SCEW sheet 13A. Environmental conditions {'/) s_ outside the containment can exceed the conditions inside the containment only with respect to temperature which could reach 326 F. (Containment temperature can reach a maximum of 279 F). The ideal set screw connectors are rated at 150 C (302 F) for an indefinite length of time (document reference 3. and 5. of SCEW sheet 13A). Outside the containment, the ambient temp. would only exceed the rated value for less than one minute and is, therefore, censidered insignificant especially since the connectors are housed in metal enclosures l and vauld likely never reach the ambient temperature. 1 3-M Scotch-Lok Connectors These devices have been identified as being installed outside the containment only. An independent laboratory has been retained by NUSCO to perform an analysis of environmental qualification of these connectors. Continued plant operation is justified since all connectors are instslied in - metal enclosures and it is unlikely that their environment would e- r reach destructive levels. The temperature transient is relatively short lived and l diminishes to less than 2000F in two ninutes. Also, the conclusion reached in the reference a) observation end stated judgement is that the 3-M Skotch-Lok connector, when compared with the Ideal Set Screw connector is a better device for mechanical integrity and lower circuit leakage.
Miscellentous Electrical Deviess Page 2 O Terminal Blocks - GE EB-5 and other types (unidentifigd) These devices have been identified as being installed only outside the containment. No specific environmental qualification has been obtained. Continued plant operation is justified, however, because the walk-through inspection indicated that these blocks would have similar characteristics to ones that successfully withstood LOCA simulation tests while energized with 525 volts AC. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices Refer to Generic Replacement Schedule 1. Butt Splices These devices have been identified as being installed only inside the containment in one valve circuit. No specific qualification has been obtained thus far, hevsver, continued plant operation is justified for the following reasons: a) Inspection disclosed that quality, spacing and enclosure of the splice would likely preclude circuit failure resulting from an accident. b) Any known failure mode will cause the valve to move to the safe position. Due to the desirability of long term operability of this equipment and in Os conformance with existing license requirements, they will be replaced with fully qualified devices Refer to Generic Replacement Schedule 1. Safety Switches, Fuse Blocks and Fuses These devices are all associated with charging pump MP18Bl. They are located in zone 9A which can reach an environment of 100% relative humidity, ! Ild F and 0.5 psig due to an accident. It is considered that the devices are adequately protected to preclude failure since they are housed in gasketed enclosures. Therefore, continued plant operation is justified. Due to the desirability of long term operability of this equipment and in conformance with existing license requirements, they will be replaced with fully qualified devices Refer to Generic Replacement Schedule 1. Reference a) NUSCO memorandum, J. M. Clark to R. J. DeRosa GRE-80-233 dated October 14, 1980. 8/21/31 (.w)
! O O- O i
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. - 335 F/96 psig l C.d l y3
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l O O- 0 I i < FIGURE 1. Specified temperature, pressure, and radiation test profile - ! FIRL Test Report F-C4020-1 i l l This profile has been designated by the vendor as f j " Confidential". Therefore, it has not been !- submitted with this package. It is available at Northeast Utilities for Auc'it, however. i t i l I t 5 I I - i i I PROFILE 3 . I ! 11/1/80 l t
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~
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- F/O psig l!
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