ML19339A621

Environ Qualification of Safety-Related Electrical Equipment. Includes App 2,providing Sys Component Evaluation Work Sheets & Justification for Continued Operation, & App 3,providing Response to 801014 Audit Rept

ML19339A621
Person / Time
Site:	Millstone
Issue date:	10/31/1980
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19339A615	List: ML19339A614 ML19339A621 ML19339A623
References
IEB-79-01B, IEB-79-1B, NUDOCS 8011040427
Download: ML19339A621 (200)

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l MILLSTONE UNIT NO. 2 i

ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT TABLE OF CONTENTS A. INTRODUCTION AND CHRON' OLOGY B. ENVIRONMENTS- l

1. CONTAINMENT PROFILES, TEMPERATURE, AND PRESSURE

2. RADIATION PROFILES

3. SUBMERGENCE

4. HUMIDITY

5. CHEMICAL SPRAY

6. AGING

7. AREAS OUTSIDE CONTAINMENT C. COMPLIANCE WITH THE JUNE 30, 1982 DEADLINE APPENDIX 1 -

MASTER LISTING OF ELECTRICAL COMPONENTS BY SYSTEM APPENDIX II - SYSTEM COMPONENT EVALUATION WORK SHEETS (SCEWS) AND JUSTIFICATIONS FOR CONTINUED OPERATION APPENDIX III - RESPONSE TO AUDIT REPORT DATED OCTOBER 14, 1980 l

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ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMFNT MILLSTONE UNIT NO. 2 l CHRONOLOGY AND REFERENCES I i r

(1) February 8, 1979 . . . . B. H. Grier letter to W. G. Counsil transmitting i I&E Bulletin No. 79-01.

i (2) March 23, 1979 . . . . . W. G. Counsil letter tc R. W. Reid ' identifying

l. unqualified SMLS.

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(3) April 6,1979 . . . . . . W. G. Counsil letter to R. W. Reid identifying qualified SMLS to be installed prior to Cycle 3

-startup.

l 4 (4) April 18, 1979 . . . . . W. G. Counsil letter to R. W. Reid identifying unqualified solenoid operating valves will have l qualified solenoids by Cycle 3 startup.

t l (5) May 8,1979 . . . . . . . "W. G. Counsil letter to R. W. Reid identifying i SMLS on Valves SI-G14, G24, G34, and G44 will i not be ' replaced; justification provided. .

1 (6) June 6, 1979 . . . . . . B. H. Grier letter to;W. G. Counsil transmitting ,

4 I&E Bulletin No. 79-OlA, regarding ASCo solenoid valves.

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(7) June 6, 1979 . . . . . . W. G. Counsil . letter to N. C. Mosely transmitting .

l- response to I&E Bulletin No. 79-01.

j i (8) September 4, 1979.. . . . W. G. Counsil letter to N. C. Mosely transmitting additional information to response to I&E Bulletin

' No. 79-01, June 6, 1979 letter.

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l (9) September 5, 1979 . . . . W. G. Counsil letter to R. W. Reid identifying-

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unqualified RID's in containment - continued i . operation justified.

(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 j response to I&E Bulletin No. 79-28/ Defective Gaskets in NAMCO SMLS.

(12) January _14, .,.v. . . .. .-B. H. Grier letter to W. G. Counsil transmitting-I&E Bulletin No.79-01B.

l (13)' January'18, 1980 . . . . W. G. Counsil letter to N. C. Mosely transmitting

! update to original I&E Bulletin No. 79-01 response

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-- additional information.

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Environmental Qualification of Electrical Equipment ,

Millstone Unit No. 2

() Page 2-(14) February 29, 1980 ... B. H. Grier letter to W. G. .Counsil transmitting Supplement to I&E Bulletin No.79-01B.

(15) March 3, 1980 ..... W. G. Counsil letter to B. H. Grier transmitting response to Items 1 - 3 to I&E Bulletin No.79-01B.

(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. Counsil 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 issues Memorandum end Order requiring SER's by February 1,1981 and total compliance by June 30, 1982.

(19) July 14, 1980 ..... NNECO representatives attend Region I clarification meeting.

(20) July 16, 1980 ..... W. G. Counsil letter to B. H. Grier update to original response to I&E Bulletin No.79-01B, March 3,1980 letter, addressing commitments made in the April 17, 1980 letter.

(21) August 26, 1980' . . . . R. T. Carlson letter to W. G. Counsil discussing j audit findings on selected components.

(22) August 29, 1980 .. .. R. A. Clark letter to W. G. Counsil transmitting

the Order for Modification of License requiring a j response by November 1,1980.

(23) September 10, 1980 .. W. G. Counsil letter to B. Wolfe (GE) requesting expedited response regarding qualification documen-tation.

(24) September 19, 1980 . . . D. G. Eisenhut letter to W. G. Counsil transmitting ,

Revised Order for Modification of License. I (25) September 30, 1980 . . . NRC issues Supplement ! to I&E Bulletin No.79-01B. j i

(26) October 1, 1980 .... D. G. Elsenhut letter to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits requesting pertinent information. relative to environmental qualification testing.

h 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 regarding .

qualification documentation.

i (28) October 14, 1980 . . . . R. T. Carlson letter to W. G. Counsil discussing findings of audit regarding comparison of qualifica-1 tion documentation to plant components.

(29) October 20, 1980 . . . . NNECO representative responds to request of NRC Project Manager to provide status of the response to the Order.

(30) October 24, 1980 . . . . B. H. Grier letter to W. G. Counsil transmitting Supplement 3 to I&E Bulletin No.79-01B.

1 (31) Oc tober 24, 1980 . . . . R. A. Clark letter to W. G. Counsil transmitting an immediately effective order regarding modifications to the license and Technical Specifications.

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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 Reference (1), References (2) thro"gh (5) were subitted to notify the Commission that certain stem-

' moun ud limit switches were lacking the requisite qualification, and identified corrective action and justification for continued operation.

By Reference (6), the NRC issued I&E Bulletin No.79-01A, regarding ASCo solenoid valves. NNECO's initial response to the provisions of Items 1 through 3 of Reference (1) was docketed by Reference (7) and supplemented by Reference (8). References (9) and (10) were submitted in conformance with Item 4 of Reference (1) and discussed the qualification status of  ;

resistance temperature detectors used to monitor containment air temperatures.

Justification for contirued operation was provided. Reference (11) docketed l

a response to I&E Bulletin No. 79-28 regarding NAMCo stem-mounted limited switches.

l The issue of environmental qualification was escalated to a higher priority status upon issuance of Reference (12). An indication of the magnitude of l this task can be obtained by reviewing the attached chronology. It is i important to recognize that NNECO resources have been strained significantly, not merely because Of the amount of equipment requiring qualification l dccumentation, but alo because of the numerous changes and conflicts in NRC l

guidance documents on thn subject. To support this position, the attached l g cho nology is discussed to specify instances where such conflicts have arisen i and to identify the applicability of these reference documents as of this writing.

Supplemental information in the form of System Component Evaluation Work Sheets (SCEWS) was provided in Reference (13). For each component, information 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 Ref erence (13).

The first supplement to Reference (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 Question 5, in which the Staff stated that TMI lessons-learned equipment was not to be addressed. The response to Question 9 is also of significance as the Staff 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 compnents. The response to Question 18 of Reference (25) discusses the differences between NUREG-0588 and NUREG-0578 regarding the calculation of radiation source terms.

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By References (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 information regarding the radiation service conditions and temperature and pressure profiles which remain applicable as shown in Appendix II.

In Reference (18), the Commissioners issued the Memorandum and Order, and required the NRC Staff to issue Safety Evaluation Reports by February 1, 1981.

It is NNECO's intention that the report will be the foundation for a favorable 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 longer 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.

Commitments made in Reference (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 Reference (21). No items of non-compliance were identified during the 16-hour verification inspection.

In Reference (22), the Staff 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 difficulty 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 respect to the requirements of this document were discussed in the forwarding letter. NNECO reemphasizes that extreme difficulties are encountered when the NRC issues documents which revise the scope of a major effor? which are required by order to be submitted merely one month from the isstance of Reference (25).

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(_,) By Reference (26), the Staff 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 respons, 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 of Inspection and Enforcement. No items of non-compliance were identified.

A response is provided as Appendix III to this report.

Reference (29) identifies a call between NNECO representatives and the 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 NRC 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 saf ety-related electrical equipment, which is possible even if certain provisions of the qualification requirements cannot be ful-filled by documentation.

By Reference (30), the Staf f transmitted Supplement 3 to I6E Bulletin No.

,., 79-OlB. This document delayed the schedule for submittal of all qualification

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documentation regarding TMI Action Plan equipment until February 1, 1981.

Similarly, the qualification information for equipment requited to achieve and maintain a cold shutdown condition is not required until February 1, 1981. NNECO's position regarding these changes is being provided now and will be supplemented by February 1,1981.

By Reference (31), NNECO received an immediately effective Order which modified the license and the Technical Specifications. June 30, 1982 hac 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 maintain them at central locations. Steps are being taken to comply with these requirements on schedule.

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B.1 CONTAINMENT PROFILES. TEMPERAR1RE AND PRESSURE O The desien easis temeeratere and gressere ceueitiens ter 8111stene Unit No. 2 result 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 qua11fication 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 profiles is consistent with applicable NRC requirements.

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J B.2 ENVIRONMENTS - RADIATION PROFILES By letter dated December 31, 1979, Northeast Nuclear Energy Company (NNECO) docketed the results of calculations 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 W' ork Sheets (SCEWS) of Appendix II as appropriate.

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B.3 ENVIRONMENTS - SUBMERGENCE 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 representation 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.

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E B.4 ENVIRONMENTS - HUMIDITY O ~

The relative humidity of the air surrounding the Category 1 equipment has been conservatively assumed to be 100% for the duration of the elevated temperature and pressure condition resulting from a IDCA or a HELB unless otherwise noted in the System Component Evaluation Work Sheets (SCEWS) in Appendix II. Additionally, it is assumed that the entire compartment associated with HELB instantly saturates with steam, even though the Category 1 equipment may be separated by long distances and torturous pathways from the HELB. This approach assures that an appropriate level of conservatism has been employed in this evaluation.

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t B.5 ENVIRONMENIS - CHEMICAL SPRAY O Equipment subject to harsh chemical environments due to actuation of the containment spray system is identified on the System Component Evaluation Work Sheets (SCEWS). The operation of this system is detailed ~ in ':he Millstone Unit No. 2 FSAR, Section 6.4.

The composition of _ the spray is less than 2400 ppm boron es derived from the Refueling Water Storage Tank.

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B.6 ENVIR0!MENTS - AGING O Equipment which is subjected to harsh environments caused by a LOCA or 3

j 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 int-o this category, i Normal radiation and temperature data were obtained from plant operating i records and from in-service surveys conducted during the summer of 1980. 1 Operating temperature surveys were performed during the hottest days of j 1980 in the areas surrounding the Category 1 equipment and this information represents the Normal Maximum Temperature that the equipment would be subjected to throughout its design life. Additional conservatism was added  ;

in the aging analysis by assuming that the equipment would be exposed )

continually to these temperatures, giving no credit to seasonal and i operational differences in ambient temperatures.

Identification of age sensitive 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 in the System Component Evaluation Work Sheets (SCEWS). In conformance with the Commission's May 23, 1980 Order, NUSCO O has committed to a program of replacement, 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.

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B.7 AREAS OUTSIDE CONTAIl0Gurr 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 presaure environments.

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C. COMPLIANCE WITH THE JUNE 30, 1982 DEADLINE O 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 or NUREG-0588."

There are electrical components identified in the Appendix Il for which total conformance to all applicable qualification requirements cannot i be demonstrated at this time. In certain instances, a replacement I 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, I relocating equipment, determining that the components are not required for accident mitigation, determining that the component has acceptable failure modes, or demonstrating that the adverse impact associated with component failure is acceptable. Adoption of one of the above alternatives rather than replacement continues to assure conformance with the June 30, 1982 deadline.

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i APPENDICES

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1. MASTER LISTING OF ELECTRICAL COMPONENTS BY SYSTEM In fulfillment of one of the objectives of the environmental qualification program effort, a master listing of all safety-related electrical components, segregated by system, has been generated. This document will facilitate future decisions regarding qualification requirements and serves as a foundation for the qualification effort. .This Appendix is bound separate from the balance of this report.

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-OlB 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 the Appendix. Only those components which are required to mitigate the effects of a LOCA or HELB which results in the harsh environment for that component are addressed. The profiles to which the equipment must be qualified are included in Appendix II.

(3 s/ III. RESPONSE TO AUDIT REPORT DATED OCTOBER 14, 1980 For completeness, a response to the site audit findings is hereby provided.

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1-DOCKET NO. 50-336

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4 1 I NORTHEAST NUCLEAR ENERGY COMPANY

MILLSTONE UNIT NO. 2

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i l APPENDIX II i

SYSTEM COMPONENT EVALUATION WORK SHEETS (SCEWS) l AND JUSTIFICATIONS FOR CONTINUED OPERATION i

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CONTENTS O-U SYSTEM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPONENTS INSIDE THE CONTAINMENT 2A - 38A SYSTEM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPO'7.NTS OUTSIDE THE CONTAINMENT 1B - 122B SYSidM COMPONENT EVALUATION WORK SHEETS - SHEETS INCLUDING COMPONENTS REQUIRED ONLY BY PLANT EMERGENCY 1C - 20C

, OPERATING PROCEDURES MISCELLAllEOUS ELECTRICAL EQUIPMENT DOCUMENT KEFERENCE LIST SUPPLEMENT ENVIRONMENTAL TEMPERATURE PRESSURE PROFILES PROFILE NUMBERS INCLUDING 4

2-42 l

TEST DATA TABLES TABLE NUMBERS I INCLUDING 2A - 6B A

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Facifk Unit:

': Millstone Euclear Pr. Sta.

Two S " TEM COMPONh;NT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTAT O! REF* QUAL. OUTSTANDING EQUIPMENT DESCRI'1 ION EINIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Containment Operating Continuous Continuous I- 2.e) Sequential Plant ID No.: EB2,WB2,EB4, Time .Iest ECl,EC3,WC3,WC5 Component: Low Voltage Temperature Profile 18 Profile 36 D 2.d) Simultan -

Power & Control Electri- ( F) eous Test cal Penetrations Manufacture: Pressure Profile 19 D 2.d) Simultan-CO! J (PSIA) Profile 37 eous Test g

s Relative Simultan-Model Number:

7852-10000 Humidity (%) 100 100 1. 2.d) eous Test Function: Maintain elec-trical continuity through ' Chemical the cont. struct. Spray 2400 PIM 3000 PPM F 2.c) Simultan-Boron Boron eous Test Accuracy:

Not Required Sequential Service:Various Low Radiation 8 Voltage Power & Control 9.4 x 106 R 2.2 x 10 M 2.a) Test Ckts.

Incation: Containment Aging Plant Design Sequential EL 14'6" 2.b) 40 Years )40 Years Life Test Flood Level Elev: (-)l4'4* NA NA NA NA 5,ubmergence NA Above Flood Level: Yes X Mn-

• Documentation

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 2-A

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Fr.ci Millstone Nuclear Pr. Sta. ,

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATIOt REF* QUAL. OUTSTANDING l EQUIPMENT DESCRIPTION ENVIRONMENT

' METHOD ITEMS Parama.ter . Spec. Qual. Spec. Qucl. _

Passivs Devict See System: Various Operating Continuous Continuous 1.

Time Qual'.fied Qual.

Plant ID No.: By design Box-TemperatureProfile 18 Simultaneous.

Component: Electrical _ 4 D Test Penetration Term, Blocks ( F)

Note 2 Profile 19 simultaneous.

Manufacture: General Pressure Test Electric Co. (PSIA)

Simultaneous.

Model Number: CR-151 Relative 100 100 1. 4 Function: To terminate connections to electrica1 ' Chemical 2400 PPM Note 1 p penetrations Spray Note 1.

Boron Note 1 Accuracy: Not Required Radiation 4 D

Service: Various circuits 9.4 x 10 6R 1.2X10 R M er t r search 1'lant See Incation: Containment Aging es gn summary EL 14'-6" 40 yrs.

Life sheet Flood Ievel Elev:(-)l4'4" NA NA Above Flood Level: Yes X Suhnergence NA 'NA NA Mn

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References:

Notes:1. Term. blocks are mounted in sealed boxes. No direct impingement. Protection considered adequate.to

1. Bechtel Tech. Spec. 7604-E-34 prevent failure due to an accident.

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2. Loca Qualification nrofiles from Doc. Ref. 4.

320 260

. 4. GE Ltr. G-EH-8-16 dated 2/2/78 Ten F 260 320 340 75 21 Term Block Locatest Forwarded Press PSIG 21 75 103 by G.E. Ltr. R.F. Thibault to R. Derosa dated 12/1,/79 100 100 100 100 100 RH %

G.E. Ltr. G-EH-9-1-141 dated 10/18/79 1.5 Days 1.5 Hrs. 3 Hrs. 4.5 Hrs. 8 Day Duration 3-A 11-1-80

SUMMARY

SHEET NO.

SCEW SHEET NO. 3A O

C EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT

SUMMARY

l MILLSTONE UNIT 2 EQUIPMENT: Electrical penetration terminal blocks -

General Electric CR 151 (containment El. 14' 6")

MANUFACTURER: General Electric Company i

I QUALIFICATION DISCREPANCY: Qualification is complete except for aging.

n SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATICN:

These terminal blocks were furnished as an integral part of the GE electrical penetrations. They provide the means of terminating field wiring on the penetrations.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging' analysis for this equipment.

Justification for continued operation is that these terminal blocks have been used only about five of their 40 years of specified life. Also, periodic testing and preventive maintenance will verify qualification of aging.

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Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

Simulta-System: Electrical Operating neous Plant ID No.: Time Test Continuous Continuous .1. e)

Component: Low Voltage Temperature Profile 18

( F) Profile 2 D 4.c) Simultaneous Power Cable Test Manufacture: Anaconda Pressure Prot 11e 19 (PSIA) Profile 2 D 4.c) Simultaneous Test Model Number: EPR Insul, Relative Humidity (%) 100 100 1 4.a) Simultaneous CSPE Jacket Test Function: Wirewyas for Low Voltage Motors, ' chemical ~

2400 PPM 3000 PPM F 4.a) Simultaneous D.C. Systems, Heater, etc. Spray Test Accuracy: Not Required boron Boron Note 1 Service: 480 V, 120 V AC, Radiation 8 Sequential 1.5 x 108 R 2X10 R 2 4.b) 125 VDC Circuits Test Incation: Containment Aging Plant Simulated Design Sequential 40 Years 40 Years Life 4.f) Test Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Sulunergence NA NA NA NA NA nn

• Documentation

References:

Notes:

1. Bechtel Tec% ical Spec. 7604-E-17 1. Chemical spray consists of:

2. NUSCO Memo. D.W. Miller to R.J. DeRosa, 3000 PPM Boron as Boric Acid NEE-79-E-281 Dated 5/21/79 0.064 Molar Sodium Thiosulfate 4

3 FIRL Test Report F-C-4350-3 Adjusted with Sodium Hydroxide to a PH of 10.5 at Room Tem a) Page 3-2, Sec. 3.3 d) Page 3-1 b) Appendix C e) Page 3-3 c) Fig. 2 f) Attachment dated May,1977 4-A 11-1-80

Faci ( Milletonn Nuclear Pr. Sta. ( '(

Unit: Two SYSTEM COMPO!!ENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTAT Of REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _,

Simulta-System: Electrical Operating Plant ID No.: Time Continuous Continuous 1. 4 (d) neous

, Test Component: Control Cable Temperature Profile 18 Simultan-Profile 3 D 4. M eous Test Manufacture: Kerite Pressure Profile 19 (PSIA) Profile 3 D 4.(a) Simultan-eous Test Model Number: FR Insul Relative 100 100 1. 4.(a) Simultan-FR Jacket Humidity (%) eous Test Function: Wireways for control & Low Level Pwr " Chemical 3000 PPM Ckts Spray 2400 PPM Boron F 4. (b) Simultan-Accuracy: Boron Note 1 eous Test Not Required Service: Radiation 1.5 x 10 8 R 2X10 R 2. 4.(c) Simultan-Various Control and Low eous Test Level Pwr Ckts.

Iocation: Aging Containment Simulated Sequen* !al 40 Years 40 Yrs 1. Test Flood Level Elev:(-)l4 '4" Above Flood Level: Yes X Submergence t NA un N NA NA NA g NA

• Documentation

References:

Notes:

1. Bechtel Technical Spec. 7604-E-18 1. Chemical Spray Consist of:

2. hDSCO Memo. D.W. Miller to R.J. DeRosa 0.28 Molar H3 B0 (3000 PPM Boron) 3 NEE-79-E-281 Dated 5/21/79

4. FRIL Test Report F-C4020-1 0.064 Molar NA223 80 (a) Fig. 1 N20H to make a PH of 10.5 at 77 F (t,) Page 3-1

{c) Page 5-2

, (d) Page 6-1 11-1-80

5. Kerite Engineering Memornadum 178A, May 1, 1979 5-A

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SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATIGri RE_'* QUAL. OUTSTANDING ENVIRONMENT ITSMS EQUIPMENT LESCRIPTION METHOD Parameter Spec. Qual. Spec. Qual. 6 Operating Continuous Continuous 1. 4.d) Note. 1 System: Instrumentation Ple t ID No.: Time Component + Instrument Temperature Profile 18 Profile 4 D 4.c) Simultaneous Cable ( F) Test

• Pressure Profile 19 Simul taneous Manufacture:

Profile 4 D 4.c)

The Rockbestos Co. (CERRO) (PSIA) Test

• Model Number: Relative 1. 4.b) Simultancour 100 100 XLPE Insul-Neoprene Jacket Humidity (%) Test * '!

Function:

Wireways for Instrumenta- ~ Chemical 2400 PPM 3000 PPM F 4.c) Simultaneous tion Ckts. Spray Test

• Boron Boron Accuracy:

Not Required Service: Radiation 8 4.a) Sequential 1.5 x 10 8R 2X10 R K.

General Instrumentation Test

• Iocation: Containment Aging Simulated " cential 40 Years 40 Years 1. 4.e) lest

• Flood Level Elev:(-)l4 '4" NA NA Suhnergence NA NA Above Flood Level: Yes X NA m

e.: : Notes:

• Documentation Refar_

1. Bechtel Technica' 'fpec. 7604-E-19A

• Insulation only ,

2. 1. Cable involves low current only. Continuous

3. operation is inherent.

4. CERRO Cert. Report dated 2/1/77 (e) Page 3, par. V

('b) Page 4, par. V (c) LOCA Profile page 8 (d) Page 1 6-A 11-1-80 (e) Page 2

Fccility:; [ ] tsne Nuclear Pr. Sta.

[.7m Unit: Two V SYSTEM COMPONENT Ei, ION W s't SHEET ,! )

Docket: 50-336 ENVIRONMENT DOCL E iTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS HEMIOD Parameter Spec. Qual. __ Spec .

Qual.

Syctems Instrumentation Operating Continuous Continuous 1. 3.d Simultaneou  ;

Plant ID No.: Time Test Component: Instrument Cab: eTemperature Profile Profile D 3.a) Simultaneou  ;

( F) 18 3 Test Manufacture: Kerite Pressure (PSIA) Profile Profile D 3.a Simultaneou  ;

Model Number: 600V 19 3 Test Relative 100 100 1. 3.a) Simultaneoun Humidity (%) Test Function: Wireways '

for Instrumentatiog Chemical 2400 ppm 3000 ppm Circuits Spray Boron F 3.b) Simultaneou:6

• ' N te 1 Test

• Not Required 8

Service: Radiation 1.5X'lb8R 2 X 10 R 2. 3.c) Simultaneous General Instrumentation Test Incation: Aging 40 yrs. Simulated Sequential Containment 40 yrs. 1. 4. Test Flood Ievel Elev:-14'4" N/A N/A N/A N/A N/A Above Flood Level: YesX Subnergence nn CDocumentation

References:

Notes: 1. Chemical Spray consists of: 0.28 Molar

1. NUSCO Standard Specification for Instrument Cable H3 B03 (3000 ppm Boron) 600 volts SP-GEE.14

2. NUSCO memo D. W. Miller to R. J. DeRosa NEE-79-E-281 0.64 Molar NA S O223 N OH to make a pH of 10.5 at 77 F dated 5/21/79

3. FIRL Test Report F-C4020-1 dated March, 1975 a) Fig. 1 c) Page 5-2 b) Page 3-1 d) Page 6-1

4. Ierite Engineering Memorandum 178A, May 1979 6-As 11/1/80

k b -(

Fccid  : Millstone Nuclear Pr. Sta.

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENT T ON REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS EE Sh. 252(H-29A) 253(H-298) Parameter Spec. Qual. Spec. Qual. _ ,

System: Post-Accident Hyd. Operating Continuous-ly one mon 60 Days 1. 4.a) Sequential Plant ID No.: Cont. Time Test H-29A, H-29B or more Component: Temperature Profile 18 (Op) Profile 5 A D 4.e) Sequential Hydrogen Recombiner (See note 1.) Test Manufacture: Pressure Profile 19 (PSIA) D Profile 5 , 4.b) Simultaneous Westinghouse ,

• Test Model Number: Relative Humidity (%) 100 100 1. 4.b) Simultaneous Dwg. No. ME-7070-1 Test Function: To limit Hydrogen existing in the ' chemical F 4.b) Simultaneous containment Spray 2400 PPM 2500 PPM Boron Test Accuracy: Boron.

Not Required Service: Radiation 1.5 x 10 R 2X10 R 2. 4.c) Sequential Test Incation: Aging Plant esign Sequential '

EL14'-6" (H-29A) 40 yrs. 40 yrs. We 4.d) Test EL38'-6" (H-29B)

Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: Yes X Subnergence Mn

" Documentation

References:

Notes:

o

1. Bechtel Tech. Spec. 7604-M-510, Page 3,4 1. Containment Temp deminishes to 200 F approx.

2. NUSCO memo, D.W. Miller to R.J. DeRosa, NEE-79-E-281 dated 5/21/79. b hour after a Loca: H. Recombic.s .- is started 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after a Loca

3. Spray consisted of 2500 PPM Boron as Boric Westinghouse WCAP7709-L and Suppl. 1-7 2.

4. acid with Sodium Hydroxide added to give a PH

'(a) Suppl 3, Par. 3,1.2 (b) Suppl 2, Page 3-24 (Test 2,3) of 10 (c) Suppl 2, Par. 3.6.2 (d) Suppl 6, Par. 6.3.2 (c) Temp. vs time profile forwarded by Westinghouse 7-A ltr. NE U 3546 dated Oct. 1, 1980. 11-1-80

Faci ( Millstone Nuclcar Pr. Sta. t {

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMEtTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS EESH. 206-209 Parameter Spec. Qual. Spec. Qual.

System: Cont. Air Eecire. Operating Note 2 1 Yr. 1. 4.d) Sequential Plant ID No.: F-14A, F-14B Time Test p rfe[t:

~

Temperature Profile 18 ntainment Table 2A, 4.c) Simultan-Air Recirculation Fans

( F) D 2B eous Test Manufacture: Pressure Profile 19 Westinghouse Table 2A, (PSIA) 2B D 4.c) Simultan-eous Test Model Number: Westinghouse Relative Syle Nc. 7189007 Humidity (%) 100 100 1. 4.b) Simultan-Function: eous Test Cool Containment Air ' Chemical 9.5 PH Spray Spray F 4.b) Simultan-2400 PPM Accuracy: Boron Note 1 eous Test Not Required Service: Containment Radiation 8 1.5 x 108 R 2X10 K 4.a) Sequential Air Recirculation System- Test ation: Containment ^91^9 40 Yrs. Plant 4.e) Sequential 40 Yrs.

El. 2'-0", 36'-0" esign Test Life Flood Level Elev: (-)l4'4" NA NA NA NA NA Above Flood Level: Yes X Submergence No

• Documentation

References:

Notes:

1. Bechtel Technical Sepc. 7604-M-501 1. The chemistry environment 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)

Westinghouse WCAP 7829 with soduim hydroxide.

4. The units shall be designed to operate for Ta) Page 10,14 (c) Page 33,35 2.

(b) Page 15, 37 (d) Page 3 20 hrs. at peak incident conditions and 7 days (e) Page 16 at 15 PSIG, 200 F.

8-A 11-1-80

+

FaciI y: Milletene Nuclear Pr. Sta. ( ' , (s/

~

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIRONMENT DOCUME! AT ON REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION Parameter Spec. Qual. Spec. Qual.

System: Operating Continuous 1 yr. I- 3.b) simultaneout Plant ID No.: F-18A, F-18B Time test Component: Post Incident Temperature Profile lo Profile 25 Recirculation Fans ( F) D 3.b) simultaneour test Manufacture: Joy Mfg. Co. Pressure Profile 19 (Reliance Electric Co. (PSIA) Profile 25 D 3.b) simultaneouo test Motor)

Model Number:24-17-5-3500 Relative simultaneout Special S/NGF15745, 15746 Humidity (%) 100 100 1. 3.d) test Function: Containment Air Mixing Chemical Spray 2400 PPM Note 1 F 3.c) simultaenoun test Accuracy: Not Required Boron 8 sequential Service: Post Incident Radiation 1.5 x 10 R 1X10 R 2*

Recirculation - 460V 3.e) test Incation: Containment Aging 40 yrs. 40 yrs. 1. 3.a) se quential El. 14'-6" test Flood Level Elev:(-)l4'4?

Above Flood Level: YesX Subnergence NA NA NA NA NA no

• Documentation

References:

Notes:

1. Bechtel Technical Spec. 7604-M-507 1. Chemical spray per IEEE 323, page 19 (3000 PPM Boron) .

2. NUSCO memo, D. W. Miller to R. J. DeRosa, NEE-79-E-281 dated 5/21/79

3. . Joy Qualification 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

n ih Faci ( O ': Millstone Nuclear Pr. Sta. f(d \

SYSTEM COMPONENT EVALUATION WORK SHEET (OQ Unit: Two Docket: 50-336 QUAL. OUTSTA!GING ENVIRONMENT DOCUMENTATION REF*

~ EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Sequential System: Various operating Time P Continuoun P 5 Plant ID No.: Various Component: Stem mounted Temperature Profile 18 Profile 6 D 5.a) Simultaneous limit switches ( F) Test Manufacture: NAMCO Pressure Profile 19 (PSIA) Profile 6 5.a) Simultaneous D

Test Model Number: EA-180 Relative 100 100 1. 5.b) Simultaneous Humidity (%) Test Function: Valve control

• Chemical interlocks and position 2400 PPM F 5.b) Simultaneous Spray Note 1 indication Boron Test Accuracy:

Not Required Service: Vari us air Radiation g 8

4. 5.c) Sequential 1.5 x 10 R 2.04X16 R Test operated and motor operated valves Test & Gasket Aging 40 yrs.

Location: 40 yrs. except P.D.L. 2 Analysis replacement, Inside Containment req. every gasket (2 yrs.) 2 yrc.

Flood Level Elev:(-)l4'4" NA NA NA NA Above Flood Level: Yes X Submergence NA Nn Notes:

• Documentation

References:

1. The spray consisted of boric acid, water, sodium

1. FSAR safety analysis (Ammendment 20) thoiosulfate and sodium hydroxide-PH-10 (3000 PPM Boron

2. Wyle Report 17436-3 2. Model EA-180 limit switches replaced originally-

3. installed limit switches on the following valves:

4. NUSCO memo, D. Miller to R. DeRosa, NEE-79-E-281 EB-88 SI-614 SI-618 CH-515 dated 5/21/79 CH-516 EB-89 SI-624 SI-628

5. Vendor qual. report, plant file MRIR #1-26-79 CH-517 AC-5 SI-634 SI-638 (a) Fig. 1, page 11 o f 11 CH-518 AC-6 SI-644 SI-648 (b) Page 9 of 11 CH-519 11-1-80 (c) Page 2 of 11 f - - a __

im .~

r: Milletona Nuclear Pr. Sta. [ (D ((

Facia SYSTEM COMPONENT EVALUATION WORK SHEET Unii:: Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTATION REF*

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Sequential System: Various Operating 5 Test Time P Continuous P Plant ID No.: Various Component: Stem mounted TemperatureProfile 18 5.a) Simultan-( F) Profile 7 D cous Test limit switches Manufacture: NAMCO Pressure Profile 19 Profile 7 D 5.a) Simultan-(PSIA) eous Test Model number: EA-740 Relative 100 1. 5.b) Simultan-100 Humidity (%) eous Test Function: Valve control interlocks and position ' Chemical Spray 2400 PPM Note 1 F 5.c) Sircultan-indication Boron eous Test Accuracy:

Not required Service: Various air Radiation g Sequential 8 4. 5.b) operated and motor 1.5 x 10 R 2.04X10 R Test d valves 40 yrs. Test & Gasket deation, Aging except P.D.L. 2 Analysis replacement Containment 40 yrs. . gasket req'd every

'M vrn.)  ? yr.

Flood Lavel Elev:(-)14'4" NA NA NA NA NA Above Flood Level: Yes X Suhnergence nn I Notes:

• Documentation

References:

The spray was composed of boric acid, water, 1.

1. FSAR safety analysis (Ammendment 20) sodium thiosulfate, and sodium hydroxide,

2. Wyle Report 17436-3 PH between 10 & 11 (3000 PPM Boron).

3. 2. Model EA-740 limit switches replaced originally

4. NUSCO memo, D. Miller to R. DeRosa, NEE-79-E-281 installed limit switches on the following valves:

5-21-79 HV-9230 HV-9151 HV-1060

5. Vendor qual. report, plant file MRIR #1-26-79 HV-9125 HV-1064 tiV-8380 a) Fig. 1, Page 11..of 12 CH-506 HV-1062 HV-8378 b) Page 7 of 12 c) Page 8 of 12 11-A 11-1-80 d) Page 3 of 1

FaciK Milletone Nuclear Pr. Sta. h [

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMFNTAT ON REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION 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

( F) Profile 8 D 5.b) Simultaneous Condactor Seal Assembles Test for SMLS's Manufacture: Pressure Profile 19 (PSIA) Profile 9 3 5.c) Simultaneous CONAX Test Relative 100 100 1. 5.d) Simultaneous Model Number: Part No. Test N-11061-32, N-llOOl-33 Humidity (%)

Function:

Provide.a sealed cable " Chemical Spray 2400 PPM Note 2 F 5.d) Simultaneous entrance for SMLS's Test Accuracy: Boron Not required 8 Sequential Service: Radiation 1.5X108R 1.5X10 R 4. 5.a)

Test Valve limit switches Location: Aging Sequential Containment 40 Years 40 Years PDL 6 Test Flood Ievel Elev:(-)l4"4" NA NA NA Above Flood Level: Yes X Subnergence NA NA no

• Documentation

References:

Notes:

1. All modules must be compatible with Fig. 5.3.1

1. FSAR safety analysis (Ammendment 20) The test data base configuration was subjected

2. to the test profile given in Fig. 5.3.2.

3. Chemical spray consisted ~of boron.and NA0H with

4. NUSCO memo D. Miller-to R. DeRosa, NEE-79-E-281 2.

, dated 5/21/79 a PH of 10.5 (3000 PPM Boron)

3. Assemblies were purchased under NUSCO P. O. 607 386

5. CONAX qualification report IPS-409 dated 3-9-79 for qualified components a) Par. 5.1 c) Par. 5.3.2.4 b) Par. 5 3.1 & 5.3.2 d) Par 5.3.2.2

6. CONAX Qualification Report IPS-325 11-1-80 12-A

I (3

("

Facil(  : Millstone Nuclear Pr. Sta. ((/

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Pa rameter Spec. Qual. Spec. Qual.

Passive System: Electrical Operating Design Device See Plant ID No.: Time Require- Qualified Qual.

Continuous Continuous :nent By Design Box Temperature Profile 18 Simulta Component: Set screw D 3. neous Connectors FF) _ 3 Test Manufacture: Ideal Pressure Profile 19 Simulta-(PSIA) 3 D neous Test Simulta-n xlel Number: Cat. No. Relative 100 3. neous Humidity (%) 100 3 30-210 and 30-211 Test Function: Splice Assemblies ' Chemical 3. Simulta-Spray 2400 PPM 2640 PPM F neous Accuracy: Not required Boron Boron Test Service: Valve limit Radiation 2.4 x 107 R 3 x 10 8.R 4. 5.a) Analysis switch circuits Location: Various Loca- Aging Plant tions inside containment' 9366 yrs. Design 40 yrs. at 1200F Life 5.a) Analysis Flood Level Elev:(-)l4'4" NA Above Flood Level: YesX Subnergence NA NA NA NA Mn

• Documentation

References:

Notes:

1.

2.

3. NUSCO memoranda GEE-79-214, GEE-78-358, GEE-79-271

4. NUSCO memo D. W. Miller to R. DeRosa NEE-79-E-281 dated 5/21/79

5. WYLE Report 17436-1 dated Oct. 8, 1980 a) Page 21 13-A 11-1-80

/ p (3

Faci ( C I Millstone Nuclear Pr. Sta. (b SYSTEM COMPONENT EVALUATION WORK SHEET

(

Unit: Two Docket: 50-336 ENVIRONMENT DOCUMEttfAT ON REF* . QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

simultaneous System: Chem.& Vol. Control Operating P- Continuous P 3.a) Test Plant ID No.: HY-518 Time HY-519 Component: Selenoid TemperatureProfile 18 Profile 10 3.b) Simultaneous Operated Valves (OF) D Test Manufacture: Pressure Profile 19 Profile 10 3.b) Simultaneous D Test ASCO (PSIA)

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 ' Chemical 3.d) Simultaneous Spray 2400 PPM B y Test Accuracy: Not Required Boron Service: Charging Line Radiation 1.5X108R 2 x 108 R 4. 3.e) Se uential Te t Distr. Valves Location: Containment Aging Req. maint.

El. 8'-6" Sequential performed 40 Years 4.4 Years PDL 3 Test every 3 yrs Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Suhnergence NA NA NA- NA NA Mn

• 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 Par. 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-o0

,e3 Facil(  : Millstono Nuclear Pr. Sta. ('

SYSTEM COMPONENT EVALUATION WORK SIIEET Unit: Two Docket: 50-336 ENVIRONMENT DOCLMENTATIOI REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION i METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Chem. & Vol. Cont. Operating P Continuous P 3.a) Simultaneous Plant ID No.: HY-517 Time Test Component: Solenoid Temperature Profile ?.8 Profile 10 D 3.b) Simultaneous Operated Valve (OF) Test Manufacture: ASCO Pressure Profile 19 Profile 10 3.b) Simultaneous (PSIA) est D

Relative 100 100 D 3.c) Simultaneous Model Number: Type 200-381-6RF Humidity (%) Test Function: Pilot Valve for CH-517 ' Chemical 3.d) Simultaneous Spray 2400 PPM 3 Test p

Accuracy: Not Required Boron Service: Aux. Spray Radiation 1.5X100R r 2 x 10 s 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, Flood Level Elev:(-)14"4" Above Flood Level: Yes X Suhnergence NA NA NA NA NA nn CDocumentation

References:

Notes:

1. 1. Originally installed valve replaced May, 1979 (Refer to

2. W. C. Counsil letter to R. Reid dated 4/18/79)

3. ASCO Teet Report No. AQS 21678/TR Rev. B 2. SMLS Type EA-180 a) Appt dix 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

4. NUSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79 11-1-80 15-A

O) Millstone Nuclear Pr. Sta. ( ~\ I]

(pQ Fccih[

Unit: Two

(*: SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMEdrATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION ~ METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Approx. 5 System: Chem. 6 Vol. Control Operatin9 Sec . Fol- Continuous 5. 3.a)- Simultaneous Time rest Plant ID No.: HV-515, lowing a HV-516 Loca.

Temperature Profile 18 Profile 10 3.b) Simultaneous Component: Sol (.noid Test Operated Valves ( F)

Pressure Profile 19 Profile 10 3.b) Simultaneous Manufacture: ASCO (PSIA) D Test 100 100 D 3.c ) Simultaneous Model Number: Type NP- Relative Test 8320A-185V Humidity (%)

Function: Pilot Valves 3.d) Simultaneous for CH-515, CH-516 " Chemical Test Spray 2400 PPM B y

, Boron Accuracy: Not Required Service: Letdown system Radiation 1.5X108R 2 x 108 R 4. 3.e) Sequential Test containment isolation Req. maint.

Incation: Containment Aging Sequential performed El. 8'-6a 3 Test every 3 yrs.

40 Years .4.4 Years PDL Flood Level Elev:(-}l4'4" NA NA NA Above Flood Level: Yes X Suhnergence NA NA Mn -

cDocumentation

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 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. Table 2 6-2 11-1-80 16-A s

-- - . . . , ~ .- .- -- - .- _ . - . - . - - - _ . - . . -. . ..

Faci.[ Millstona. Nuclear Pr. Sta. h (

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-33G ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD-Qual.

4 Parameter Spec. Qual. Spec.

Approx. 5 System: Encl. Bld'g. Filt. Sys. Operating Sec. Fol- Continuous 5. 3.a)

Plant ID No.: HV-8150, Time lowing a rest L ca.

HV-8151 Component: Solenoid Temperature Profile 18 Profile 10 3.b) Simultaneous D Test Operated Valves -( F)

Profile 19 Profile 10 J.b) Simultaneour I Manufacture: ASCO Pressure D Test (PSIA)

Model Number: Valve Type Relative 100 100 D 3.c) Simultaneoun -

Test 206-381-3RVU Humidity (t)

Function: Pilot Valves fon '

EB-88, EB-89 Chemical 3.d) Simultaneoun Spray 2400 PPM Boron B F Accuracy: Not Required Service: Containment Rad. Radiation 1.5 x 10 8R 2 x 10 8R 4. 3.e) Sequential Test Mor.. Isolation Req. maint.

Location: Containment Aging Sequential performed El. 38'-6" 40 Years . 4.4 Years PDL 3 Test every 3 yrs.

Flood Level Elev:(-)l4'4" NA E E E E Above Flood Level: Yes X Suisnergence un

• Documentation

References:

Notes:

1. 2. 1. Originally installed valves replaced during Oct. 1979 Outa ,

3. ASCO Test Report No. AQS 21678/TR Rev. B 2. SNLS Type EA-180 a) Appendix A Par. 5 b) Appendix A Fig. 9.2 I 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

5. Tech. Spec. 3.6-2 17-A 11-1-80

. . m _

t Facil( ' : Millstonc !!uclear Pr. Sta.

SYSTEM COMPOMENT EVALUATION WORK SHEET Units Two Docket: 50-336 ENVIRONMENT DOCUMET ATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

Approx. 5 System: Note 1. Operating Sec . Fol . Continuous 2 1.a) Simultaneous.

Plant ID No.: HV-9230, Time lowing a Test HV-9125, CH 506, HV-9151 Loca.

Component: Solenoid Temperature Profile 18 Profile 10 Simultaneous Operated Valves (OF) D 1.b) Test Manufacture: ASCO Pressure Profile 19 Profile 10 Simultaneous (PSIA) D 1.b) Test Model Number: Relative 100 100 D 1.c) Simultaneous NP-206-381-6F Humidity (%) Test Function: Pilot Valves for LRR 43.1, GR-ll .1, ' Chemical Simultaneous CH-506, SSP-16.1 Spray 2400 PPM B F 1.d) Test Accuracy: Not Required . Boron Service: Containmv nt Radiation 1.5 x 10 8R 2 x 10 8R K 1.e) Sequential Test Isolation Incation: Containment Aging Req. maint.

El. 3'-0", 3'-6", 8'-6", Sequential performed

.2'-6" 40 Years 4.4 Years PDL 1 Test every 3 yrs; Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: Yes X Suhnergence Mn __

• Documentation

References:

Notes:

1. LRR-Clean Liquid 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 & Volume Control System c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 SSP-Drain System e) Appendix D 2. Originally installed valves were replaced during

2. Tech. Spec. Table 3.6-2 October, 1979 outage

3. SMLS Type EA-740 11-1-80 19-A

}

Faci ( Milletons Nuclear Pr. Sta. (

Unit: Two SYSTDi COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIROMMENT DOCUM TIATI N REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Approx. 5 System: Reactor Coolant Operating Sec. Fol- Continuous 4 3.a) Simultaneous Plant ID No.:HV-1064, Time lowing rest hV-1062, HV-1060 a toca.

Component: Solenoid TemperatureProfile 18 Profile 10 3.b) Simultaneoun Operated Valves (OF) 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: Pilot 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 108 R 2 x 108 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:(-)l4'4" Above Flood Level: Yes Submergence un X No 5 CDocumentation

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 d) 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 9-29-80 GEE-80-710 20-A 11-1-80

Faci Unit: ( Two Millstone Nuclear Pr. Sta. (

SYSTEM COMPChT.NT. EVALUATION WORK SHEET

(

Docket: 50-336 ENVIRONMENT DOCUMEtTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Encl. Bldg.Filtrati cnoperating P Continuous P 3.a) Simultaneous Plant ID No.:HV-8380, Time Test HV-8378 Component: Solenoid TemperatureProfile 18 Profile 10 3.b) Simultaneous Operated Valves (OF) D Test Manufacture: ASCO Pressure Profile 19 Profile 10 3.b) Simultaneoua (PSIA) D Test Model Number: Valve Type Relative 100 100 D 3.c) Simultaneoua NP-8344 B58V Humidity (%) Test Function: Pilot Valves for EB-91, EB-100. ' Chemical 3.d) Simultaneoua Spray 2400 PPM B F Test Accuracy: Not Required Boron Service: Hydrogen Purge Radiation 1.5 x 810 R 2 x 10 8R 4. 3.e) Sequential Valves Test Req. maint.

Location: Containment Aging Sequential performed El. 38'-6" 40 Years 4.4 Years PDL 3 Test every 3 yrs.

~

. Flood Level Elev:(-)l4'4" A NA l Above Flood Level: YesX Suhnergence nn

1. 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 i c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D

4. NOSCO Memo D. W. Miller to R. DeRosa NEE-79-E-281, dated 5/21/79 11-1-80 21-A

m i

( y/

Faci ( v':Millstons Nuclear Pr. Sta. (

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: S0-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS-EE SH 40(S1614) 68(S1634) 66(S1624) 70(S1644) Parameter Spec. Qual. Spec. Qual.

Note 1. Note 1. Note 1. Note 1. Note 1.

System: Safety Injection Operating Plant ID No.:SI 614, SI Time 624, SI 634, SI 644 Component: Valve Motor Temperature Profile 18 Profile 11 4.b) Simultaneous D Test Operators (OF)

Mann?acture: Limitorque- Pressure Profile 19 Profile llA Simultaneous (PSIA) D 4.f) Test Relative 100 100 1. 4.a)~ Simultaneous Model Number: Serial Nos. Test 157040,157041, 042, Humidity (%)

043 Function:h5*

For SI-61 ,SI-634 Chemical Note 2. 4.d) Simultaneous 2400 PPM F Test SI-644 Spray 8Y" Accuracy: Not Required Service: SI Tank Isola- Radiation 1.5 x 10 8R 2.04 x 1083 K 4.c) Sequential Test tion ation: Containment Aging p g

.40 Yrs. 40 Yrs. Design 4.e) Test Life Flood Level I 1ev: (-)14'4" NA NA NA NA NA Above Flood Level: Yes X Sutunergence Mn cDocumentation

References:

Notes:

1. Bechtel Technical Specs 7604-M-223A, 7604-E-40, 1. Not Applicable. Valves are administrative 1y controlled 7604-E-llB open (accident position) - Tech Spec 3 5-1A

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 11-1-80 23-A

m l

Faci { '/ Millstone Nuclear Pr. Sta. (v SYSTEM COMPONENT EVALUATION WORK SHEET

( -

Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMEh"r PSTHOD ITEMS EE SH 39(S1651) 62(S1652)

Parameter Spec. Qual. Spec. Qual.

794 CY.

Safety Injection Operating Note 1. Post Env. Note 1. 4.e) Sequential System 4195 CY. Test Plant ID No.: SI 651, Time SI-652 Total Component: Valve Motor TemperatureProfile 18 Profile 11 Simultaneous Operators (OF) D 4.g) rest Manufacture : Limitorque Pressure Profile 19 Profile 11 i 4.b) Simultaneous D Test (PSIA)

Model Number: Serial Nos. Relative 100 100 1. 4.a) Simultaneous 155532, 155533 Humidity (s) Test Function: Operators for 4.d) Simultaneous

~

SI-651, SI-652 ' Chemical Note 2.

Spray F Test 2400 PPM Accuracy: Not Required Boron Service: Shutdown Cooling Radiation 1.5 x 108 R 2.04 x 108n K 4.c) Sequential Isolation Valves Test Incation: Containment Aging Approx. Plant Sequential El. O'-0"' (-)l'-6" 40 Yrs. 40 Yrs. Design 4.f) Test Life Flood Level Elev: (-) l4 ' 4 " NA NA NA NA NA Above Flood Level: Yes X Submergence Nn 8 Documentation

References:

Notes:

1. Bechtel Technical Specs. 7604-M-223A, 1. Valves are interlocked to prevent opening during 7604-E-40, 7604-E-11B operation (Ref. Logic Diagram 25203-28115, SH 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 11-1-00 g) Fig. 5 24-A

Millstone Nuclear Pr. Stc. ( (

Faci ( SYSTEM COMPONENT EVALUATION WORK SHEET Unit:. Two Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MET!!OD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Safety Injection Operating Within 5 Plant ID No.: HY618,628 Time Sec. After Continuous 2 1.a) Simultaneous 638,648 a toca. Test Component: Solenoid Temperature Profile 18 Profile 10 1.b) Simultaneous.

D Test Operated Valves (OF)

Manufacture: ASCO Pressure Profile 19 Profile 10 1.b) Simultaneous (PSIA) Test Model Number: Valve Types Relative 100 100 D 1.c) Simultaneous.

Humidity (%) Test NP-206-381-6RF Function: Pilot Valves for SI618,SI628,SI638 ' Chemical SI648 Spray 2400 PPM Simultaneout B F 1.d)

Accuracy: Not Required Boron Test Radiation Sequential Service Safety Injection Tank Test and Fill Valves 1.5 x 10 8R 2 x 108 R K 1.e) Tast Aging Req. maint.

Location: Containment Sequential performed El. O'-0" 40 Years 4.4 Years PDL 1 Test every 3 yrs, Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: Yesx Suhnergence un CDocumentation

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

2. Tech. Spec. Table 3.6-2 25-A 11-1-80

e ..

A Fcci( Ur: Millstons Nuclear Pr. Sta. [' '

(O C/

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET

-Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION EINIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Reactor Coolant Operating Simultaneous Plant ID No.: PT-100X,Y Time :ontinuous Continuous 2 1 Test Temperature Profile '

Component: Profile Pressure Transmitter (OF) 16, 18 318'F D 34 Simultaneous Test Manufacture: Pressure 1 Foxboro (PSIA) Profile Profile Simultaneout 16, 19 90 PSI D 34 Test Model Number: E-11GM Relative i Simultaneout Humidity (%) 100% Profile 100% D 34 Test Function: Pressurizer S**

' Chemical R:ater Control Spray M 00 PPM F summary Accident Monitoring Be sht. 27A Accuracy:

• 0.25% F.S. S**

Service: Pressurizer Radiation 1.5 x 10 R 8 'K summary Pressure Monitoring sht. 27A Aging See Iocation: Containment summary 40 yrs. P.D.L.

El. (-) 5 ' -0" ' sht. 27A Flood Ievel Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: Yes X Suhnergence Nn 8 Documentation

References:

Notes:

1. Foxboro Test Report Q9-6005 - i -

2. MPII FSAR Table 7.5.2 f 11-1-80 27A

I l

SUMMARY

SHEET NO. 27A A

SCEV SHEET NO.

r.

( ) -

t , EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT

SUMMARY

MILLSTONE UNIT 2

' PT-100X, 100Y; PRESSURIZER PRESSURE, CONTROL MEASUREMENT CHANNELS EQUIPMENT:

MANUFACTURER: FOXBORO Model E11GM S/N 2602021, 2602022 QUALIFICATION DISCREPANCY: These components lack documented qualification concerning their resistance to chemical spray, radiation and time / temperature aging.

p j C/ SAFETY FUNCTION AND JUSTIFICATION L FOR CONTINUED OPERATION

PT-100Y provides signal input for the post accident monitoring, subcooling margin monitor. Both these components 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 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. 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, they will be replaced with fully qualified components.

This replacement will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date. An independent laboratory has been retained by NUSCO to ,

l provide radiation and time / temperature aging analysis for this equipment.

()

LJ

%wn '

I

Facif Millstone Nuclear Pr. Sta, h (,

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUM ITATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRON!CNT METHOD ITEMS Parameter' Spec. Qual. Spec. Qual. _ ,

Simulta-Continuous Continuous 5 1 neous System: Main Steam Operating Test Plant ID No. : LT-5274 Time LT 5272 Component: Differential Temperature Profile 15' (Oy) Profile 18 17 Table D 1,4 Simultaneous Pressure Transmitter 6A, 6B Test Manufacture: Pressure Profile 15 '

Foxboro (PSIA) Profile 19 17 Table D 1,4 Simultaneous 6A, 6B Test Relative Profile 15 .

Model Number: E-13DM Simultaneous Hamidity(%) 17 Table D 1,4 100%

6A, 6B Test Function: Input for 3 element feedwater ' Chemical Profile 15 ,

control accident monitorir g Pray ,

S 2400 ppm 17 Table F 1,4 Simultaneous Accuracy: Boron -

6A, 6B , G Test 0.5% Span Service: Steam Generator Radiation 8 " '"

Level Monitoring 1.5 x 10 8R 2.2x10 R K 2,3 Test Location: Containment Aging 40 yrs. P.D.L. s ry El. 14'-6" sht. 28A Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: Yes X Subnergence un

• 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 T3-1097 Radiation Test of E-10 Series amplifiers standard and radiation resistant pg. 3.

3. Fpxboro 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 /;.

5. MPII FSAR Table 7.5.2

.1-1-80 28A

SIDetARY SHEET NO. 28A 28A SCEW SHEET NO.

(N , EQUIPMENT ENVIROl0 ENTAL QUALIFICATION DISCREPANT EQUIPMENT EV.0talY MILLSTONE UNIT 2 STEAM GENERATOR LEVEL MONITORING, DIFFERENTIAL PRESSURE EQUIPMENT:

TRANSMITTERS LT-5272, 5274 i

MANUFACTURER: FOXBORO E-13DM S/N 3220857, 3220858 QUALIFICATION DISCREPANCY:

Radiation and time / temperature aging are not addressed in the manufacturer's qualification test reports.

rn Qv- SAFETY FUNCTION AND JUSTIriCATION FOR CONTINUED OPERATIO!i: ,

These components provide signal input for the 3 element fedwater control system and control room steam generator level indication. The specification for these components identified 40 years as the desired design life. An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis tor this equipment.

l Due to the present age of this equipment, the results of the aging analysis  !

are not critical to establish reasonable assurance that the equipment will perform its function. l

Faci Millstone Nuclear Pr. Sta. (

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIROMMENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _ ,

Operating Continuous Continuous Simultaneous System: Main Steam 1 Test Time 5 Plant ID No.: W 3A

^ Temperature P.rofile 15, Component: 1,4 Simultaneous (OF) Profile 18 17, Table D Differential Pressure Test Transmitter 6A, 6B Manufacture: Pressure P.rofile 15 Simultaneous Profile 19 17 Table D 1,4 Foxboro 6A, 6B Test Relative Profile 15.

Model Number: E-13DM 1 * * " "" """ "

Humidity (%) 100%

6A, 6B Test Function:

R.P.S. Input ' Chemical Profile 15

& Accident Monitoring Spray 2400 ppm F 1,4 Simultaneous 17 Table Accuracy: Boron 6A, 6Be G Test 0.5%

Service: Steam Generator Radiation Sequential 2.2x10 R. 2,3 Test Level Monitoring 1.5 x 10 8R K Aging gee Location: Containment summary 40 yrs. P.D.L.

El. 16'-0" sht. 29A ,

Flood Level Elev:(-)l4'4" NA NA NA NA NA Above Flood Level: YesX Submergence Mn

• 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 T3-1097 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/RRIJ Type pg.

4. FIRL Test Report F-C3635 " Maximum Credible Accident Environment Test of Four Tranaitters Figure 4.

5. MPII FSAR Table 7.5.2 29A 11-1-80

SUMMARY

SHEET NO. 29A SCEW SHEET NO. 29A L , EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUM 1AR?

MILLSTONE UNIT 2 EQUIPMENT: STEAM GENERATOR LEVEL MONITORING, DIFFERENTIAL PRESSURE TRANSMITYERS LT1113A, 1123A MANUFACTURER: FOXBORO E-12DM S/N 3220855, 3220856 QUALIFICATION DISCREPANCY: Radiation and time /remperature aging are not addressed in the manufacturer's qualification test reports.

h i

SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

These components provide RPS input for a reactor trip on lau :te_m generator level, and control room steam generator level indication. The specification for these components identified 40 years as.the desired design life. An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Due to the present age of this equipment, the results of the aging analysis are not critical to establish reasonable assurance that the equipment vill perform its function.

O*

%g

SUMARY SHEET NO. 30A 30A SCEW SHEET NO.

Q y ,

EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SID9fARY t MILLSTONE UNIT 2 Pressurizer level (tontrol measurement channels) LT-110X,110Y EQUIPMENT:

differential pressure transmitters FOXBORO E13DH S/N 2648245, 2648246 MANUFACTURER:

QUALIFICATION DISCREPANCY: These components lack documented qualification concerning their resistance to chemical spray, radiation and time / temperature' aging.

SAFETY FUNCTION AND JUSTIFICATION v FOR CONTINUED OPERATION:

This equipment provides, charging pump control cucuit 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 A

all pressurizer heaters on a high or low-low level condition respectively.

low pressurizer level signal from these. components also provides a backup signal to start all charging pumps. This equipment provides control signals only and is 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 event of a worse case component failure. Due to the desirability of long term operability of this equipment, they will be replaced Mth qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982 assuming that procurement delays do.not preclude replacement by that date.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

0 l S.

l

6-4 Facif'is Millstona Nuclear Pr. Sta.

Unit: Two

[OO SYSTEM COMPONENT EVALUATION WORK SHEET

{'Q Docket: 50-336 DOCUt.1TATION REF* QUAL. OUTSTAFDING ENVIRO'IMENT EQUIT' MENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Continuous Continuous simultaneous System: Main Steam Operating Test 2 1 Plant ID No.:PT-1013 A,B, Time C D PT-1023 A,B,C,D 1 domponent: Temperature Pressure Transmitter (OF) Proflie 18 Profile Simultaneous 318*F D 34 Toye Manufacture: Pressure 1 (PSIA) Profile 19 Foxboro Profile Simultaneous 90 PSI D 34 T,,e 1

Model Number: Relative Profile Simultaneous Humidity (%) 100% D 34 Test E-ll 100%

Function: See ESAS & RPS ' Chemical 2400 PPM summary

& Accident Monitoring Spray F Boron sht. 31A Accuracy:

~ 0.5% Span See Service: Steam Generator Radiation 8 K s imwna ry Pressure Monitoring 1.5 x 10 R ,

sht. 31A See I4 cation: Containment Aging summary 40 yrs. P.D.L.

El. 16'-0" sht. ?lA Flood Level Elev: (-)l4'4" NA NA ?U.-- NA NA Above Flood Level Yes X Submergence nn

• Documentation

References:

Notes:

1. Foxboro Test Report Q9-6005

2. MPII FSAR Table 7.5.2 11-1-80 31-A

SUMMAa? SHEET NO.

31A SCEW SHEET NO.

[)

v s- . EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT GUMMaRY MILLSTONE UNIT 2 EQUIPMENT:

STEAM GENERATOR PRESSURE (PROTECTIVE MEASUREMENTS CHANNELS)

PT-1013/1023 A, B, C, D MANUFACTURER: Foxboro E-ll Pressure Transmitter S/No's 2602030, 2602031, 2602032, 2602033, 2602034, 2602035, 2602036, 2602037 QUALIFICATION DISCREPANCY:

This equipment lacks documented qualification concerning their resistance to chemical spray, r ' tation and time / temperature aging.

(o) SAFETY FUNCTION AND JUSTIFICATION

'C FOR CONTINUED OPERATION:

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 feedwater 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 Iech. Spec. requirements. The trip delay 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 perform their intended functions; reactor trip, mainsteam and feedwater isolation. Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment.

30, 1982, This will be accomplished as soon as practicable, prior to June date. assuming that procurement delays do not preclude replacement by that An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging for this equipment.

pm

\J m

d

.~_ _ -

4

1. l Fcci 7: Millstone Nuclear Pr. Sta. [# {

Unit:- Two f SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. CNTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

System: Reactor Coolant Operating Continuous 2 1 Simultaneous Continuog Test Plant ID No.:PT102 A,B, Time C,D _,_.

Temperature 1 Component:

( F) Profile 16 Profile Simultaneou  ;

Pressure Transmitter 18 318,F D 34 Test Pressure 1 Manufacture:

Foxboro Profile 16 Profile (PSIA) 19 90 PSI D 34 Simultaneou 5 Toct 1

Model Humbert Relative .

E-11 Humidity (%) 100% 100% D Profile Simultaneou  ;

34 Test Funct!.on:ESAS & Reactor see Pro t< etive System and ' Chemical ,

summary Spray y Accident Monitoring Boron sht. 32A Accuracy:

See Service: Pressurizer Radiation l pressure monitoring 1.5 x 108 R K sh 3 See Location: Containment Aging summan El. 7'-0" 40 yrs. P.D.L. sht. 32A Flood Level Elev:(-)l4'4" A NA NA NA Above Flood Level: Yes X Submergence Nn CDocumentation

References:

N_otes:

1. Foxboro Test Report Q9-6005

2. MPIl FSAR Table 7.5.2 11-1-80 3M

o 32A StBetARY EEEET NO.

SCEW SHEET NO. 32A O, -

EQUIPMENT ENVIROIOU M AL QUALIFICATION DIscmEPAF;f EQUIPMENT SIDetARY KILLSTONE 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 QJALIFICATION DISCREPANCY: This equipment lacks documented qus11fication concerning their resistance to chemical spray, radiation and time / temperature aging.

/

N(' SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

These componen*4 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 of wrability of this equipment.they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming tha'. procurement delays do not preclude replacement by that date.

An independent labo 4 tory has been contracted by NUSCO to provide radiation and time / temperature apng analysis for this equipment. l I

O O c

/%

F;:cilitys ( ( Jcten2 Nuclear Pr. Sta. [ [g]

TION WORK SHEET \ _/

Unit: Two' ~ SYSTEM COMPONENT Et....

Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.

Iynten: Reactor Coolant Operating Sequential Piant ID No.: RC-422,414, Time Continuous Continuour 1 2 Test 415,416,417,423,424,425 Component: Solenoid Tenperature Simulta-( F) 346*F D 2c neous Valves Profile 18 Test Manufacture Pressure Simulta-VALCOR (PSIA) Profile 19 113PSIG D 2c neous Mod:al Number: Test V526-6042-3A , Simult'a-V526-6043-3A relative Humidity (t) 'neous 100 100 D 2c Test .

Function: Reactor Head ZZOO ppm

' Otemical Simulta-and Pressurizer neous Venting Spray 2400 ppm .h8[t$$S0 223 Accurzcy: N/A '

Boron Note 1 F 2c Test Radiation Sequential Service:

1.5X108R 2X108R K 2b Test Aging Sequential Incstion: CTMT 40 years 40 years PDL 2a,2b Test 38 '6" elev.

Flood Ievel Elev a(--)l4 '4" NA NA NA Above Flood Level: Yes X Submergence NA NA m

CDocumentation Rcferences: Notes:

1. The solution consisu d of 2,200 ppm boron as

1. NUREG 0578 item 2.1.9 boric acid (II 3BO

2. Valcor Engineering Qualification Test Report 3 ) in colution with 0.064 melar sodium thiosulfate (NA S 03) buUered QR52600-515 with sodium hydroxide (NAOH)y 2to make a ph

a. Appendix I of 10.5 at room temperature.

b. Appendix III

c. Appendix IV

~

34a 11-1-80

Facility:p(V4 tone Nuclear Pr. Sta.

Two. SYSTEM COMPONENT u TION WORK SHEET {j Unit Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION MEW OD ITEMS Parameter Spec. Qual. Spec. Qual.

Cy; tem: Reactor Coolant Operating Plant ID No.: RC414,415 Time Sequential continuous Contine.,us 2 1 Test 416,417,422,423,424,425 Simulta-Cr-nanant Electrical Temperature neous Connector (OF)

Profile 18 340 F D Profile 33 Test

^

simulta-Manufacture LITTON Pressurc neous (PSIA)

Prorile 19 105PSIG D Profile 33 Test Modsl Number:

CIR06VI-20-15S Plug Simulta-CIR02VI-20-15P Receptacle nelative Humidity (%) neous 100 100 D Profile 33 Test Function: Electrical -

Simulta-Connector ' Osemical 2400 ppm ~3000 ppm neous Spray

' Boron Boron F Ic Test Accuracy: N/A Sequential Service RCS Venting Radiation Solenoid Valves 1.5X108R 2X108R K la Test Incation: CTMT Aging Sequential 38'6" Test

, 40 years 40 years PDL lb Flood Imvel Elev:(-)14'4" NA NA NA NA Above Flood Imvel Yes X Submergence NA no (Documentation

References:

Notes:

1. Qualification Test of Electrical Connectors under A simulated 1DCA/DBE be sequential exposure to environments of thermal aging, background radiation, containment pressurization, vibration, radiation (accident 1cvel), steam and chemical spray.

2. NUREG 0578 item 2.1.9

a. Appendix B b. Paragraph 5.1 and 5.2 11-1-80

c. Paragraph 5.6 35a

[p [

Facility ( ctens Nuclear Pr. Sta.

Two SYSTEM COMPONENT E. v TION WORK SHEET Unit Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTATION REF*

EQUIPMENT DESCRIPTION ME'ntOD ITEMS Parameter Spec. Qual. Spec. Qual. _

Simulta-Containment Operating neous Sy; tem Plant ID No. : ED3,ED8,ED9, Time Continuous Continuous 1. 2.c) Test WD3,WDS,WD9 Simulta-Component: Instrumentatior Temperature D. 2.d) neous

( F) Profile Profile Electrical Penetrations 18 38 Test Manufactures CONAX E ssure Simulta-(PSIA) Profile Profile neous -

Modal Number: 7852-10000 19 38 D. 2.d) Test Simulta-nelhtive neous Hurddity(%) 2.d) Test .

100 100 1.-

Function: Maintain elec- ~

Simulta-trical continuity through " Chemical neous the cont. struct. Spray 2400 PPM 6200 PPM Accurrcy: Not required

' Boron Boron F. 2.e) Test Radiation Sequential Service: Various instru-6 8 9.4 x 10 R 2.0 x 10 R M.

• ) Test mentation circuits Aging Plant Incstion: Containment Design Sequential EL 14'6" 2.a) Test c 40 Yrs. > 40 Yrs. Life

, Flood Level Elev:(-)14'4" NA NA NA NA Above Flood Level: Yes X Sutunergence NA un Notes:

i Documentation

References:

1, NUSCO Specification 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 l e) Par. 5.8.1.2 Page 23 .

36A 11-1-80 _

Fccility [ tone Nuclear Pr. Sta. (

ON WORK SHEET h (-)

Unit: Two SYSTEM COMPONENT EW Docket: 50-336 ATION REF* QOAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION ME.MIOD ITEMS Parameter Spec. Qual. Spec. Qual.

"" *" ~

Sy:; tem: Rad. Monitoring Operating g Plant ID No.: ZlRM8240/ Time Continuous Continuous (P.A.M.) 1.a) Test B,C - Z2RM8241/B,C Simulta-Component: Coaxial cable Temperature neous (op) D 1.a) Test Profile 18 Profil. 39 Manufr_cture Pressure Simulta-Rockbestos Co. (PSIA) neous Modal Number RSS 6-104 Profile 19 Profile 39 D 1.a) Test Design Simulta-Relative Require- neous Humidity (%)

10% ment 1.a) Test .

Function: Rad monitoring ~

' chemical Simulta-cabling Spray 2400 PPM 3000 PPM neous Accuracy: Not required

' Boron Boron F 1.a) Test Service: Low level Pimliation Sequential 8

signal circuits 1.5 x 10 8 R 2 x 10 R K,L 1.b) Test Aging Plant Loc 2 tion: Containment Sequential Design

, 40 Yrs. 40 Yrs. Life 1.c) Test Flood Level Elev:(-)14'4" NA Above Flood Level: Yes X Subnergence NA NA NA NA un CDocumentation

References:

Notes:

1. Rockbestos report, " Qualification of firewall III coaxial constructions dated January 18, 1978".

a) Page 2, Par. IV b) Isomedix report dated December 27, 1977 c) Page 2, Par. II 37-A 11-1-80

(

Facility:( C etone Nuclear Pr. Sta. (

Two SYSTEM COMPONENT Ew _-,. TION WORK SHEET Unit Docket 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. O(frSTANDING EQUIPMEfff DESCRIPTION MEntoD ITEMS Parameter Spec. Qual. Spec. Qual.

System Simulta-CyatemJ ost Accident Mon. Operating Design neous Plant 13 No. : T356, T357 Time Continuous Continuous (P.A.M.) 1.a) Test Simulta-Component: Terminal block Temperature neous

( F)

Profile 18 Profile 40 D 1.a) Test Manuf ctures Weidmuller Pressure Simulta-Terminations Inc. (PSIA) neous Modal Number: Type SAK4 Profile 19 Profile 40 D 1.a) Test Relative Design Simulta-Require- neous Humidity (%)

100 100 ment 1.a) Test ,

Function: Termination of ~

monitoring circuits ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous

' Boron Boron F 1.a) Test Accuracy:

Service: Containment sump Radiation Sequential level monitors 1.5 x 10 R 2.07x108R 8 K,L 1.b) Test Incation: Containment Aging Plant Design Sequential 40 Yrs. 40 Yrs. Life 1.c),2. Test Flood IAtvel Elev:(-)14 '4" Above Flood Level: Yes X Submergence NA NA N. , NA NA no i CDocumentation

References:

Notes:

1. FRC final report F-C5205-3 a) Page 4-7 b) Appendix C c) Appendix B

2. Weidmuller letter dated June 10, 1980 38-A 11-1-80

Faci Milletont Nucitar Pr. Sta. [ '

SYSTEM COMPONbt,T EVALUATION WORK SHEET Unit: Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTATION REF*

ZQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Passive Device See System: Various Operating Continu-Time ous Continuous 1. Qualified Qual.

Plant ID No.: By Design Box EI""lD*"* "'

Costponent: Electrical Temperature Profile 3., A., I, est 1enetration Term. ( F) 2, Blocks 26 Note 1.

Manufacture: . General Pressure Electric Company (PSIA) 3., A., I* Simultaneous H Note 1. 2. Test Relative Simultaneous Model Number: CR-151 nst 100 100 1. 2.

functiunt To terminate Connections to Elec- ' Chemical NA NA NA NA NA trical Penetiations Spray Accuracy:

'Not Required.

Service: Radiation NA NA NA NA NA

arious Plant See s> cation: Enclosure Aging summary 40 yrs. Design Bldg. EL 14'6.. Life sheet Zone A25, A26 Flood Level Elev:

Above Flood Level: Yes Submergence Mn 8 Documentation

References:

Notes: 1. Qualification Profiles from Doc. Ref. 2.

1. Bechtel Tech. Spec. 7604-E-34 Temp F 260 320 340 320 260

2. GE Ltrs. G-EH-8-16 Dated 2/2/78 21 75 103 75 21 Press PSIG G-EH-9-141 Dated 10/18/79 RH% 100 100 100 100 100 Term. Block Loca Test Forwarled by G.E. Ltr., 1 5 Days 1.5 Hrs. 3 Hrs. 4.5 Hrs. 8 Dafs Duration R. F. Thibault to R. DeRosa Dated 12/14/s)

3. FSAR Amendment 17 11-1-80 1-B

SUMMARY

SHEET NO.

1B

-- SCEW SHEET NO.

O EQUIPMENT ENVIRONMENTAL QUALIFICATION

- DISCREPANT EQUIPMENT

SUMMARY

. MILLSTONE UNIT 2

?,

i l DIN Electrical Penetration. terminal blocks -

General Electric CR 151 (Enclosure Buidling El. 14' 6")

l i

l e eral Electric Company MANUFACTURER:

I d.

QUALIFICATION DISCREPANCY:

Qualification is complete except for aging.

bD SAFETY FUNCTION AND JUSTIFICATION F0". CONTINUED OPERATION:

These terminal blocks were furnished as an integral part of the GE electrical penetrations. They provide the means of terminating field wiring on the penetrations.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Justification for continued operation is tbat these terminal blocks have been used only about five of-their 40 years of specified life. Also, periodic testing and proventive maintenance will verify qualification of aging.

1 i

d Q{

4

o _ .

Fzci i Millstona Nuc'. car Pr. Sta. (

Unit: yo SYSTEM COMPONENT EVALUATIOH WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION EUVIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Passive System: Electric Plant ID No.:

Operating Time Continu-ously Contin-uously 1.

}ied ual.

Design Box Temperature Simulta-Component: 5000 V

( F) Profile Profile A neous Power Cable Test 24 35 2.a)

Manufacture: General Pressure Profile 35 Simulta-Cable Corp. (PSIA) A neous Note 1) 2.a)

H Table 3 Test Simulta-Model Number: EPR insul. Relative neous Hypalon Jacket Humidity (%) 100 100 1. 2.a)

Test Function: Wireways __

for Medium Voltage ~ Chemical NA NA NA NA NA Motors & Power Sources Sprhy Accuracy:

Service: Radiation Sequential 4160 V Systems lx10 7 R 5x107R 1. 2.a) Test Location: Aging 40 yrs. At least Various Plant Areas design 3 Analysis 0 yrs 11f, Outside Containment _

Flo'd Level Elev:

Above Flood Level: Yes Submergence nn (Documentation

References:

Notes: 1) No Safety Related 5000 V Cable in Areas

1. Bechtel Technical Spec. 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 Labora.ories letter in response reference:

174365-018 dated October 24, 1980 and

'Telemn dated October 29, 19 80 11-1-80 2-B

k ~

.s (o

Fccil(

.O Milletone Nuclear Pr. Sta.

( /

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTA ION REF*

EQUIPMENT DESCRIPTION METEOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-System: Electrical Operating Continu- Continuous neous

1. ~2.c)

Time ous Plant ID No.:

Component: Control Temperature A, D Simultaneous Cable ( F) Profile 20 Profile 3 2.a) Test Manufacture: Pressure Kerite (pgrA} 2.a) Simultaneous Note 1. Profile 3 A Tone Model Number: Relative 100 1. 2.a) Simultaneous Fr Insul. Fr Jacket Humidity (%) 100 Test Function: Wireways for Control and Low Level ' Chemical NA NA NA NA NA Pwr. Ckts. Spray Accuracy:

Not Required Service: Radiation Simultaneous Various Control and 8 2x108R 1. 2.b) Test Low Level Pwr. Ckts, lx10 R Location: Aging 3 Sequential 40 yrs. Simulated 1.

General Plant 40 Yrs. Test

-Areas Outside Contain- i ment Flood Level Elev:

Above Flood Level: Yes Sulznergence Mn Notes: 1. Environmental pressure is less than

• Documentation

References:

2PSIG for about 13 sec. This is insignificant.

1. Bechtel Technical Spec. 7604-E-18

2. Franklin Institute Report F-C4020 1 a) Fig. 1 b) Page 5-2 c) Page 6-1

5. -Kerite Engineering Memorandum 178A, May 1, 1979 11-1-80 3-B

. ~ - ___

(,

Fcci( v: Millstona Nuclear Pr Sta. ( -

(

Unit: Two SYSTEM COMPO2ENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT met ATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

mu a-System: Electric Operating Continu- Continuous ne s Plant ID No.: Time ous 1. 2.d)

Component: Low Voltage Temperature Power Cable ( F) .iProfile 2 A, D Simultaneous Profile 20 2.a) Test Manufacture: Pressure Anaconda (psy3) Profile 2 Simultaneous Note 1. 7. 1.a) Test Model Number: Relative EPR Insul. CSPE Jacket Humidity (%) 100 100 1. 2.a) Simultaneous est Function: Wireways for Low Voltage Motors, ~ Chemical D.C. Systems, Heaters, Spray Simultaneout Accuracy: Etc. NA NA NA NA Test Not Required Service: 480 ., 120 VAC, Radiation Sequential 8

125 VDC Circums 1x107R 2x10 R 1. 2.b) Test Location: General Plant Aging Areas Outside contain- 40 yrs. Simulated 1. 2.f) Sequential ment 40 Yrs. Test Flood Level Elev:

Above Flood Level: Yes Sutraergence

_ nn CDocumentation

References:

Notes: 1. Environmental pressure is less than 2PSIG

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

FaciI Unit: Two

Millstona Nuclear Pr. Sta. (

SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS y Parameter Spec. Qual. Spec. Qual. _,

System: Instrumentation Operating Continu- Continu-Plant ID No.: Time ous ous 1. 2.a) Note 1 Component: Instrument Temperature Cable (OF) Profile 20 Profile 4 A,D Simultaneout 2.b) Test

• Manufacture: Pressure Rockbestos Co. (psra)

(Cerro) Note 2. Profile 4 A Simultaneout 2.b) Test

• Model Numberi Relative XLPE Insul-Neoprene .<idity (%) 100 100 1. 2.c) Simultaneour Function: Jacket Test

• Wireways for Instru- ' Chemical mentation Ckts Spray NA NA NA NA NA Accuracy:

Not Required Service: Radiation g General Instrumentation 8.60x106R 2x10 R C,L 2.d) Simultaneous Test

• Location: General Plant Aging Simulated Sequential Areas Outside Contain- 40 yrs.

ment 40 yrs. 1. 2.e) Test  ;

Flood Level Elev:

Above Flood Level: Yes Subnergence no .

• 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

_ = -

[

Facility: ctone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT Ew. u TION WORK SHEET Dockz;t s 50-336 DOCUMENTATION REF* QUAL. urr5TANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _.

Sy; tem: Instrumentation Operating Continuous Continuout 1. 2.c) simultaneous Time rest Plant ID No.:

nstrument Profile Profile A,D 2.a) Simultaneous Cable 20 3 Test Manufcctures Pressure Simultaneous Kerite (PSIA) Note Prof 1T A 2.a)

Test Modal Number: 600 V 1 :4 Relative 100 100 1. 2.a) Simulta'neous Huaidity(%) Test

• Function: Wireways for '

instrumentation circuits ' chemical Spray N/A N/A N/A N/A N/A Accuracy: Not required 8 Services General Radiation 8.60 instrumentation R Incation: General plant Aging

1. 3.

areas outside the entmt. 40 yrs. Simulated Sequential

. 40 yrs, Test Flood Level Elev Above Flood Level: Yes Submergence un cDocumentation

References:

Notes:

1. NUSCO Standard Specificatin for instrument cable 1. Env ironmental pressure is less than 2 PSIG for about 13 600 volts SP-GEE-14 seconds. This is insignificant.

2. FIRL Test Report F-C 4020-1 dated March 1975 a) Fig. 1 b) Page 5-2 ,

c) Page 6-1 1

3. Kerite Engineering Memorandum 178A, May 1979 5-Ba 11/1/80

! O^

Faci [ yt Unit: Two Millstonn Nuclear Pr. Sta. ( (b SYSTEM COMPONEhT EVALUATION WORK SHEET hd Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _ ,

Must open 200 CY at System: Safety Injection Operating and stay 165 0F, Sequential Plant ID No.: SI615, Time open 100.% RH 4. 3.e) Test SI625, SI635, SI645 Component: Valve Motor Temperature 2.

Operators ( F) ll20 F max. Profile 12 A Simultaneous 3.d) Test Manufacture: Pressure 2.

Limitorque (PSIA) Profile 12 A Simultaneous H

3.d) Test Model Number: Operator Relative ., 2.

S/N 137101, 137102, Humidity (%) g Simultaneous Function: 137103, 137104 100 100 3.a) Test Operators fo- SI615, ~ Chemical SI625, SIf >e, "I645 Spray NA NA NA NA NA Accuracy:

Not Require <'

Service: Radiation LPSI Flow 4.80x106R 2.04x108R C,L Sequential 3.c) Test Locationg Encl. Lldg. Aging Plant EL.(-)5'0", W. Pipe Simulated Design Sequential Pent, Rm. Note 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev:

Above Flood Level: Yes Suhnergence

_ nn cDocumentation

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. 1 e) Par. 2.1.3 7-B

4. FSAR Sec. 6.3.3.1 & P & ID 25203-26015 11-1-80

Faci ( Millstone Nuclear Pr. Sta. [ f  :

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec .. Q .*al . 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 (OF) 1120 F max. Profile 12 g Simultaneoun #j, 3.d) Test.

Z-Manufacture: Pressure Simultaneoun Limitorque (pszg} Profile 12 g H 3.d) Test Model Number: Operator Sg Relative 1., 2, 134075, 134077, 134079, Humidity (s) A Simultaneoun Function: 134081 100 100 3.a) Test Operators for SI616, Chemical SI626, SI636, SI646 NA NA NA NA NA Spray Accuracy:

Not Requ ired Service: Radiation HPSI Flow 4.80x106R 2.04x108R C.L Sequential 3.c) Test Plant

• Location: Encl. Bldg. Aging .

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 Level: Yes Subnergence No 8 Documentation

References:

Notes: 1. ZONE

1. Bechtel Technical Spec. 7604-M-780 SI 616 A18

2. FSAR Ammendment 17 SI 626 A18

3. Limitorque Test Report B0003, 11-13-74 to 1-23-75 SI 636 A18 a) Par. 2.1.1 SI 646 A18 b) Par. 5.0

6) Par. 2.3 d) Fig. 1 e) Par. 2.1.3 8-B 11-1-80

4. FSAR Sec. 6.3.3.1,P & ID 25203-26015

A

,b Facif y( Millstone Nuclear Pr. Sta. [ \ ~

Unit: Two SYSTEM COMPOWENT EVALUATION WORK SHEET

. Docket: 50-336

-ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: Safety Injection Operating Must open 200 CY at Sequentia]

Plant ID No.: SI617, Time and stay 165 F Test SI627, SI637, SI647 open 100% RM 4. 3.e)

Component: Valve Motor Temperature 2.

( F) Simultaneous Operator ll20 F max. Profile 12 3 3.d) Test 4*

Manufacture: Pressure Limitorque (psrA} H Profile 12 Simultaneous A 3.d) Test Model Number: Operator S/N Relative 1., 2.

134076, 134078, 134080, Humidity (%) Simultaneous Ptnction: 134082 100 100 A 3.a) Test Operators for SI617, ' Chemical SI627, SI637, SI647 NA NA NA NA NA Spray Accuracy:

Not Required S:rvice: Radiation HPSI Flow 4.80x106 R 2.04x10 8R C,L Sequential 3.c Test Ix> cation : 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 Level: Yes Submergence un

• Documentation

References:

~

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 SI 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-B

g3 ps x,

[ _

Facil( i Millstone Nuclear Pr. Sta.

SYSTEM COMPot2TT EVALUATION WORK SHEET Unit: Two Docket: 50-336 ENVIRO 181ENT DOCUMENTATION RTF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS

~

METHOD Parameter Spec. Qual. Spec. Qual.

System: Chem. & Vol. Operating NA 76.5 Sec.

Control Valve must Stroke 4. S eq u e r. '

Plant ID No.: Time HV2."24 stay as is Time 3.e) Test Compnent: Valve Motor Temperature 2.

Operators ( F) 112 F max. Profile 13 A Simultaneous 3.c) Test Manufacture: Pressure Limitorque (pg73) Profile 13 2.

II A Simultaneou 3.c) Test Operator 1., 2.

Model IP r: Relative 100 Simultaneous S/N 17* 6 Humidity (%) 100 A

.d) Test etion:

erator for CH-429 ~ Chemical NA NA NA NA NA Accuracy:

Not Requ ired Service: Radiation Charging Pump Sequential 8

Discharge :1.65x10 R6 2.04x10 R u,L 3.a) Test Location: Aging Plant Encl. Bldg. Design Sequential EL.(-) 5'0", W. Pipe 40 Yrs. 40 Yrs. Life Test Pent. Rm. Zone A18 __

3.b)

Flood Level Elev:

Above Flood Level: Yes Sutraergence na CDocumentation

References:

'. lote s :

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 t) 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

Faci ( y: - \)Millstone Nuclear Pr. Sta. (- (.fV Unit: Two SYSTEM COMPONecIT EVALUATION WORK SHEET Docket: 50-336 DOCUME! ATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRO!24ENT 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 4. 3.e) Test HV6096, HV6095 Tima __

Component: Valve Temperature 2.

Motor Operators ( F) 112 F max. Profile 13 A Simultaneous 3.c) Test

• Pressure 2.

Manufacture: "" " " "

• Limitorque (PSIA)

• H 3.c) Test A

Model Number: Operator S/N Relative 1., 2.

152851, 152849 Humidity (%) 100 100 A 3.d) Simultaneous Test Function: Operators ~

for 2-RB30-1A, 2-RBj0-1B ' Chemical Spray NA NA NA NA NA Accuracy:

Not Required Service: Radiation RBCCW to RC Pumps 4.80x106R 2.04x10 8R C,L Sequential 3.a) Test Plant

' Iocation: Encl. Bldg. Aging Design Sequential EL(-) 5'0" W. Pipe Pent. Rm Zone A18 .

40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev:

Above Flood Level: 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

8) F-C 3441, Fig. 3 d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3 11-1-80 11-B

4. FSAR Table 9.4-2, Fig. 9.4-2

gs

[/l t"'

tj 'V (v)

Facilf  : Millstone Nuclear Pr. Sta.

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-3;5 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 Stroke 4* 3.e) Tests Plant ID No.: Time Stay as is HV6108, HV-6106 Time Component: Valve Temperature 2.

Motor Operators (OF) 112 F max. Profile 13 A Simultaneous 3.c) Test Manufacture: Pressure Limitorque (psig) Profile 13 2.

H Simultaneous A 3.c)

Tect Model Number: Operator Relative 1., 2.

S/N 152850, 152848 Humidity (%) 100 100 A Simultaneous Function: 3.d) Test Operators for 2-RB37 -2A ' Chemical 1 2-RB37-2B NA NA NA NA NA Spray Accuracy:

Not Requ ired Service: Radiation RC Pump Oil Clg. Water Sequential Disch. 4.80x106R 2.04x108R C,L 3.a) Test Location: Encl. Bldg. Aging Plant

(-) 5' 0 " W. Pipe Design Sequential Pent. Rm. Zone A18 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev:

Above Flood Level: 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-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 12-B

A

)

(

Faci ( Millstone Nuclear Pr. Sta. [

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT' Note 1 DOCUMENTATION REF*

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Operating NA 200 CY at System: Safety Injection 4. 3.e) Sequential SI653, Time Valve Must 165 F, Plant ID No.: Test SI654, SI655, SI656 Stay as is 100% RH~

2.

Component: Valve Motor Temperature 0 Profile 12 Simultaneous Operators (oF) ll2 F max.

A 3,d) Test Manufacture: Pressure 2.

Limitorque (pggg) g Simultaneous H Profile 12 3.d) Test

, Operator S/N Relative Nh8d $[d83,134085, Humidity (%)

{ Simultaneous ,

134228 100 100 3.a) Test TerftSrsforSI653, Chemical SI654, SI655, S1656 Spray NA NA NA NA NA

$$$'$$(t! ired 6 8 Sequential IN ftimp Discharge 3.33x10 R 2.04x10 R C,L 3.c) Test Aux. Bldg. EL Plant Aging Design Sequential Df ff6" Simulated Note 2 40 Yrs. 40 Yrs. Life 3.b) Test Flood Level Elev:

Above Flood Level: Yes Subnergence un Notes:

• Documentation

References:

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 ',.1/13/74 to 1/23/75 2. ZONE a) Par. 2.1.1 SI 653 A3 b) Par. 5.0 SI 654 A3 c) Par. 2.3 SI 655 A2 SI_656 A2 d) Fig. 1 11-1-80 e) Par. 2.1.3

4. FSAR Fig. 6.1-1 13-B

n ,-

Faci [ %[ Millstona Nuclear Pr. Sta. (U SYSTFE COMPONENT. EVALUATION WORK SHEET Unit: Two Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPPINT DESCRIPTION Parameter Spec. Qual. Spec. Qual. _

1800 CY &

Systems Aux. Feedwater Operating Intermit- 200 gY at Sequential Plant ID No.: Time tant 165 F, Note 1 3.e) Test HV5276 1007 R.H.

Component: Valve Motor Temperature 2. Simultaneous Operators ( F) Profile 22 Profile 12 A, E 3.d) Test Manufacture: Pressure Limitorque (PSIA) H Profile 12 2. Simultaneouo A 3.d) Test Model Number: Operator S/N Relative 1., 2. Simultaneous 146658, 146659 Humidity (s) 100 100 a 3.a) Test Function: Operators for FW-43A, FW-43B Chemical Spray NA NA NA NA NA Accuracy:

Not Required Service: Radiation Sequential Aux. Feedwater NA 2.04x10 R NA 3.c) Test Isolation 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 Sulxnergence No

• 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 B0 03 11/13/74 to 1/23/75 a) 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

0 Faci 2(- :

Unit: Two Millstone Nuclear Pr. Sta. (

SYSTEM COMPOWENT EVALUATION WORK SHEET Docket: S0-336 DOCUMEI TION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT Note 1 ITEMS METHOD Parameter Spec. Qual. Spec. Qual. _

76.5 Sec, Sequentiali System: Safety Injection Operating N/A Valve Must Stroke 4. 3.e) Test Plant ID No.: Time SI662, S1663 Stay as is Time ~

2.

Component: Valve Motor Temperature Simultaneon Operators (OF) lllO F max. Profile 13 3 3.c) Test Manufacture: Pressure 2. Simultaneous (PSIA) H Profile 13 Test Limitorque 3 3.c) 1., 2.

Model Number: Operator Relative 100 100 Simultaneous S/N 168874, 168875 Humidity (%) 3 3.d) Test Function: Operators for SI662, SI663 Chemical NA NA NA NA NA Spray Accuracy:

Not Requ ired Service: Radiation 3.33x106R 2x108R C,L Sequential Shutdown Heat Exchanger 3.a) Test to HPS1 Suction .

B$bg. EL (-) 45 '6',

A91 Plant Sequential c

40 Yrs. Design 3.b) Test Zone A3(S1662) 40 Yrs.

Life Zone A2((SI663)

Flood Level Elev:

Above Flood Level: Yes Subnergence Mn

• Documentation

References:

Notes:

1. Bechtel Technical Spec. 7604-M-223B 1. These components must function in a radiation (only)

2. FSAR Ammendment 17 envir nment.

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-C 3441, Fig. 3 d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3 11-1-80

4. FSAR Fig. 6.1-1 15-B

_s f' -

I

( (

Millstone Euclear Pr. Sta. [

Faci:[ SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUME[TTATIOhhREF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT Note 2 METHOD ITEMS '-

Parameter Spec. Qual. Spec. Qual.

N/A Intermit-Operating Valve Must tant-30 mia, 6. 4.b) Sequential

, System: Safety Injection Test Plant ID No.: Time Stay as is Cycles for S1411, SI412 . 9 Hrs.

Component: Valve Motor Temperature ,

Operators (OF)

NA Manufacture: Pressure Limitorque (PSIA)

NA Model Number: Operator Relative S/h 145934, 145933 Humidity (t)

Function: Operators for NA SI411, SI412~ " Chemical Spray Accuracy: NA Not Required Service: Radiation Sequential HPSI Pump Suction 5.13x105R 2.04x10 8 C 5.

Note 1. Test Incation: Aging Sequential Aux. Bldg. EL (-) Simulated Plant 40 Yrs. Design 4.a) Test 45'6" Zone A4 40 Yrs.

Life Flood Level Elev:

Above Flood Level: Yes Submergence Mn ]

Notes:

• Documentation

References:

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 environment.

b) Page 4

5. Limitorque Test Report 600376A 4/26/72 to 8/30/72 Par. 2.1 11-1-80

6. FSAR Fig. 6 1-1 16-B

4 m-- -~ +4e m +-2 4-- k. - u-4 y- '-

N _m-- --e.+4 Facilf Millstone Nuclear Pr. Sta. [ .

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spe . Qual. Spec. Qual. _ ,

76.5 Sec. 3.e) Sequential System: Main Steam- Operating Intermit- Stroke Test Time tant Time- Note 2 Plant ID No.: HV4218 500 CY Component . Valve Motor Temperature 2.

Operator ( F) Profile 20 Profile 13 A, D Simultaneous 3.c) Test Manufacture: Pressure 2.

Limitorque (PSIA) Note 1 Profile 13 A Simultaneous 3.c) Test Model Number: Operator Relative 1. 2.

S/N 156211 Humidity (%) 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 Bypass Location: Encl. Bldg. Aging Plant .

Sequential EL 38'6" West Valve Rm. 40 Yrs. 40 Yrs. Design 3.b) Test Zore A50 Life Flood Level Elev:

Above Flood Level: Yes Suhnergence un

• Documentation

References:

Notes:

1. Bechtel Technical Spec. 7604-M-223A The peak pressure environment is 1.6 psig 1.

2. FSAR Ammendment.17 t 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 and must close and stay closed.

d) F-C 3441, Par. 3.2, Page 3-3 e) F-C.3441, Par. 3.3.3 & 600376A Par. 3.1.2 11-1-80 17-B

ps p Facil(f '"-s' Millstone Nuclear Pr. Sta.

Two h

SYSTEM COMPONENT r: VALUATION WORK SHEET h)

Unit Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD 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 Temperaturel 2.

Operator ( F) Profile 20 Profile 13 A,o Simultaneous 3.c) Test Manufacture: Pressure 2.

Limitorque (PSIA) Note 1 Profile 13 A Simultaneous 3.c) Test Model Number: Operator relative 1., 2.

S/N 155207 Humidity (%) 100 100 A Simultaneous Function: 3.d) Test Operator for MS-201 ' Chemical Spray NA NA NA NA NA Accuracy:

Not Required Service: Radiation Sequential 8

Steam Gen. No. 1 to NA 2.04x10 R NA 3.a) Test Aux. Feedwater Turbine Location: Encl. Bldg. Aging Plant sequential EL-38'6" West Valve Rm. Design Test Zone A50 40 Yrs. 40 Yrs. 3.b)

Life Flood Level Elev:

Above Flood Level: Yes Suhnergence un 7

CDocumentation

References:

Notes:

1. Bechtel Technical Spec. 7604-M-223A 1. The peak presssure environment is 1.6 psig f r a durati n f ab ut 13 seconds,

3. Lmt e Te eport 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 7 '

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

m

. i' Faciki)/ r Millstone Nuclear Pr. Sta. ( ps)

/

Unit: Two SYSTEM COMPOPhMT EV1' . TION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD' ITEMS Parameter Spec. Qual. Spec. Qual. _

76.5 Sec.

System: Main Steam Operating Intermit- Stroke Sequential Plant ID No.: HV42:2 Time tant Time - Note 2 3.e) Test 500 CY Component: Valve Motor Temperature 2.

Operator ( F) Profile 2C profile .13 A, o Simultaneoas 3.c) Test Pressure 4-Manufacture:

Limitorque (PSIA) Note 1 Profile 13 3 Hmhaneous 3.c) Test Model Number: Operator Relative 1., 2.

S/N 156212 Humidity (%) 100 100 A Simultaneous Function: 3.d) Test Operator For MS-65B ' Chemical Spray NA NA NA NA NA Accuracy:

Not Required Servicc: Radiation Seq 2ential Steam Generator No. 2 NA 2.04x108R NA 3.a) Test Main Steam Isolation Location: Bypass Aging 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 Suhnergence nn

• Documentation

References:

Notes:

17 Bechtel Technical Spec. 7604-M0223A

1. The peak pressure environment is 1.8 psig for

2. FSAR Ammendment 17 "d i f d

3. Limitorque Test Report 600376A 4-26-72 to 8-30-72 Us ly dud s to wb Me $m

' "*#* E*" " "E * ** " * *** * **

pend C , F-C3440 Par. 4.0

1. 8 * * * " " " * " # #*#*

• c') F-C 3441, Fig. 3 and est close and stay closed.

d) F-C 3441, Par. 3.2, Page 3-3 e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 19-B 11-1-80

Faci { Millstone Huclear Pr. Sta. h (

Unit: Two SYSTEM COMPODENT EVALUATION WORK SHEET Docket:- 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual. m 76.5 Sec.

System: Main Steam Operating Intermit- Stroke Sequential Plant ID No.: HV4189 Time tant y Note 2 3.e) Test Component: Valve Motor Temperature 2. Simultaneous Operator -( F) Profile 21 Profile 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 Humidity (%) 100 100 A Test S/N 156208 Function: Operator 3.d)

' Chemical for MS-202 Spray NA NA NA NA NA Accuracy:

Not Required Service: Steam Gen. No.2 Radiation Sequential to Aux. Feedwater Turbine NA 2.04x10 0R NA 3.a) Test Incation: Aging Plant Encl. Bldg. EL 38'6" Design Sequential 40 Yrs. 40 Yres. Life 3.b) Test East Valve Rm. Zone A51 Flood Level Elev:

Above Flood Level: Yes Suhnergence Nn

• Documentation

References:

Notes:

1. Bechtel Technical Spec. 7604-M-223A

2. FSAR Acenendment 17 1. The peak tressure environment is 1.8 psig

3. Limitorque Test Report 6003/6A 4-26-72 to 8-30-72 for a deation 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 3441, Par. 3.2, Page 3-3 ,

e) F-C 3441, Par. 3.3.3 & 600376A Par. 3.1.2 11-1-80 20-B a

-- -. -_ = - - _ ~ - - _ _. -_. _. . . . . . . .-

).

r: Millstone Nuclecr Pr.'Sta. ( .[

Faci SYSTEM COMPONt:WT EVALUATION WORK SHEET Unit: { Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT Note 2 DOCUMENTATION REF*

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Cec . Cual. _ ,

Sequential Systems Containment Spray Operating Continu- Continuous . Note 1. 2.,4.a) Test Plant ID No.: P-43A, -Time ous 5 days (Note 3.) '

P-43B Component: 4160V Temperature .

Pump Motor (OF)

Pressure NA NA Manufacture: General NA NA NA Electric Company (PSIA)

Model Number: S/N Relative NA NA NA NA NA 8381499, 8381500 Humidity (%)

Function:

Develop Containment Chemical NA NA NA NA NA Spray, Spray Accuracy:

Not Required Radiation Sequential Service:

Containment Spray 8.67x105R 1x 10 6R C,L 2.,4.b),3. Test Location: Aux. Bldg. Aging 40 yrs. 40 yrs. 1. 2.,4.c) Sequential EL-45'6" Zone A2(MP43A) A3(MP43B) l Flood Level Elev:

Above Flood Level: Yes Suhnergence No ,

Notes: 1. FSAR Fig. 14.d-6. CS pumps are_used to control

• Documentation

References:

1. Bechtel Technical Spec. 7604-E-10, 7604-M-53. contaigntpressure.. Coucainment pressure is at 0 psig after 10 sec.(ll.6 days).

2. G.E. Ltr. 0. A. Berquis t to R.J. DeRosa, 9-22-80, 2. Pumps are subject to radiation (only) environment.

3. NUSCO memo, R.J. DeRosa to file, GEE-80-746, 10-10-80. 3. A load test for this qualification was not cenducted.

4. G.E. Topical Report, IEEE 323, Dec., 1978. Qualification based on no load test of similar motor, a)Section IV, Page 19 b)Section III, Page 6 c)- Sumary Par. a), Page iii 21-B 11-1-80

Faci  : Millstone Nuclear Pr. Sta. (b SYSTEM COMPONENT EVALUAT::ON WORK SHEET

( N.

Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Engr. Safeguard Continu- Continu-System: Room Air Recir .

Operating ous ous 1. 3.a) sequential Plant ID No.: F-15A, F-15B Time test Component: 460V Fan Motor Temperature 2.

( F) 111 F peak 250 C 3 3.b) sequential test Z.

Manuf eture: Pressure H g H H Joy Mfg. Co. (PSIA) H (Reliance flectric Co.

Motor) 1., 2.

Model Number:38-26.5-1170. Relative 100 3.c) sequential SN-G'-15747 Motor No.' Humidity (%) 100 3 test Function:600277-14 Fan Drive Chemical NA NA NA NA NA Spray Accuracy.

Not Required ****""

Service: Engr. Sfgd. Room l Radiation 8.60x106R 2.04x108R test Air Recirculation Fan C,L 3.d)

Ix> cation: Aux. Bldg. Aging 40 yrs.

sequential EL(-)45'6'? Zone A2(MF15A)- 40 E*

• at 174.8 0c 1. 3.e) test Zone A3(MF15B)

Flood Level Elev:

Above Flood Levelr Yes Sulnergence No

$ Documentation

References:

. Notes:

1. Bechtel Technical Spec. 7604-M-507

2. FSAR Ammendment 17

3. Reliance Electric Co. Summary Report NUC. 9, July 1, 1975 a) page 15 c) page 6 t) page 5 d) page 14 e) page 21 23-B 11-1-80

Faci Millstone Euclear Pr. Sta. (

SYSTEM COMPO!TtdT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS EE Sheet 29(MP41A) 31(MP41B) 30(MP41C) Parameter Spec. Qual. Spec. Qual.

180 Days-System: Safety Injection Operating Post Acc., 8320 nrs.

Time 100 Hrs /Yr.

Plant ID No.: P-41A* I sting 3. 4. Analysis P-41B, P-41C Component: 4160V Temperature gg o 2.

Safety Injection ( F) 110.5 F A 4., Note 1. Analysis Pump Motors Z.

Manufacture: Pressure 0.5 psig H

• Siemens-Allis (PSIA) A 1., 2.

Model Number: Motor S/N Relative 00 4. ,hte 2. hahsis 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 8 4.

High Pressure 3.12x10 6R 2 x 10 R C,L Tests Safety Injection S**

Location: EL-(-) 45 ' 6" Aging Zone A2(MP41A) A4(MP41B) 40 yrs. ,

A5(MP41C)

~

Flood Level Elev:

Above Flood Level: Yes Suhnergence Mn Notes: 1. The motors were designed'for an ambient of

• Documentation

References:

1. Bechtel. Technical Spec. 7604-M-761 o'nIy F.5 F less than the spec. requirement. This

~

(Combustion Engineering Spec. No. 18767-PE-410) difference is insignificant especially since the avail-

2. FSAR Ammendment 17 able data indicates the operating temp. rise is well

3. NUSCO memo, R.M. Kacich to R. DeRosa, below rated.

2. Insulation is class B, non-hygroscopic.

NEE-80-L-350 dated 8-7-80.

4. Siemen's-Allis inter-office correspondence dated October 8,1980. (revised October 16, 1980) 25-B 11-1-80

1 SUtetARY SHEET NO.-

SCEW SHEET NO. 25B

[3

(,/

y , EQUIPMENT ENVIROlOGNTAL QUALIFICATION DISCREPANT EQUIPMENT SUltiARY MILLSTONE UNIT 2 EQUIPMENT: High Pressure Safety Inject on Pump Motors P41A, P41B, P41C MANUFACTURER: Siemens-Allis QUALIFICATION DISCREPANCY:

Qualification complete except for aging SAFETY FUNCTION AND JUSTIFICATION L FOR CONTINUED OPERATION:

For LOCA (small break), the high pressure safety injection pumps are required to provide water to maintain the reactor coolant system inventory. For a steam line break, they are required to make up the shrink due to cooldown.

These pumps also supply Boron to the RCS'to maintain shutdown margin.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Justification for continued operation is that these pu.nps have used only about five of their 40 years of specified life. Also, annual and monthly surveillance testing and preventive maintenance will verify qualification of aging.

l i

1 Ov I

. . - . . . . . . ._ - .. - . - _ ~ , . ~ . , _ .- . . . . -. ~ . . . _ _ . - - . - . . . _ -. -

O -

A~

G:

Facif f: Millstone Nuclear Pr. Sta. SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS EE Sheet 32(MP42A) 33(MP42B) Parameter Spec. Qual. Spec. Qual. _ ,

6 : Irs. Post System: Safety Injection. Operating krsIYr 40,006 hrs ,

Plant ID No.: P-42A, Time Testing Note 2. 3. Analysis P-42B Component: 41'50V Temperature 2.

111 F max. 110.50F A 3., Note 1. Analysis Safety Injection Pump ( F)

Motors Pressure 2.

Manufacture:

0.5 psig H H Analysis Siemens-Allin (PSIA)

A Relative 1., 2. Analysis Model Number: Motor S/N 100 100 3., Note 3. <

8-5717-90191-2-2, 8-5117- Humidity (%) 3 Function: 90191-2-1 Pump Drive. " Chemical NA NA NA NA NA Spray Accuracy:

Not Required Service: Low Pressure Radiation Sequential Safety Injection 4.1x10 R 6 2 x 10 R 8 C,L 3. Test See Incation: Aux. BIdg. Aging 40 yrs. 1, summary EL.(-)45'6" Zone A2(MP42AL sheet A3(MP42B)

Flood Level Elev:

Above Flood Level: Yes Submergence un .

• Dncumentation

References:

Notes: 1. The. motors were' designed for an ambient of only.

i 1. Bechtel Technical Spec. 7604-M-762 0.5'F less than the spec. requirement. This difference is

_(Combustion Engineering Spec. No. 18767-PE-410) insignificant especially since the available data indicates

2. FSAR Ammendment 17 the operating temp. rise is yell 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 '

estimated for smaller breaks. . Pumps will not.be subjected to a harsh. environment until plant goes into recire.

3. Insulation is class B, non-hygroscopic.~

a 26-B 11-1-80 i

SUMMARY

SHEET NO.

SCEW SHEET NO. 26B l l

O g , EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUle(ARY MILLSTONE UNIT 2 EQUIPMENT: Low Pressure Safety Injection Pump Motors P42A, P42B HANUFACTURER: Siemens - Allis QUALIFICATION DISCREPANCY: Qualification complete except for aging SAFETY FUNCTION AND JUSTIFICATION L FOR CONTINUED 01ERATION:

For a LOCA, the Low Pressure Safety Injection Pumps are required to supply large quantities of water at low pressure to maintain the Reactor Coolant System inventory.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Justification for continued operation is that these pumps have used only about five of their 40 years of specified life. Also, annual testing and preventive maintenance will verify qualification of aging.

I

, g. x F cility: ( , atone Nuclear Pr. Sta. .[ (j SYSTEM COMPONEWT E% L.afION WORK SHEET Unit: Two Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING

-ENVIRONMENT ITEMS EQUIPMENT DESCRIPTION METHOD Parameter Spec. Qual. Spec. Qual.

Contin- Sequential System: Operating Contin- uously Test I-lant ID No.: MPllA, Time uously 5 days Note 2. 3.,4.0) (Note 1.)

MPllB, MPllC Component: RBCCW Temperature Pump Motors ( F) 110 F max. 140 F A,2 3.,5. By Design Manufacture: Pressure (PSIA) H H Gen:ral Electric Co. H H A,2 Modal Number: SK818847Al29 Relative 100 100. 1. 3.,5. By Design S/N's LG8381496,7,8 Humidity (%)

Function: RBCCW Pump Drives Chemical

^

Accuracy: .Not Required Service: 4000V Radiation NA NA NA NA NA Location: Aux. Bldg. Aging Sequential El. (-)25' 6" 40 yrs. 40 yrs. 1. 3.,4.b) Test Zone AlB Flood Level Elev:

Abova Flood Level: Yes Submergence 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-

3. G.E. Ltr. 0.A. Berquist to R.J. DeRosa, dated formed on alternate pumps to supply cooling water to Oct. 10, 1980 en RBCCW pump motors.

Dec 1978 safety related components. -

4. G.E. Topical Report,IEEE 323b) Summar.,

a)Section IV. Page 19 y Par. a), Page 111

5. G.E. Ltr. O.A. Eerquist to R.J. DeRosa on containment spray pump motors, Nov. 15, 1979

.29-B 11-1-80

n i

' s-w) f

& f\

w/

-Faciy *: Millstone Nuclear Pr. Sta.

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Docket: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTAT N REF*

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual. _

Continuous Simultaneous System: Reactor Coolant' Operating :ontinuous 2 1' Test Plant ID No.: LT-110X Time LT-110Y Component: Temperature Profile 18 318'F D Profile Simultaneoun Differential Pressure (OF) 34 Test Transmitter __

Manufacture: Pressure ,

(PSIA) Profile 19 Profile Simultaneoun Foxbor D 34 Test

. 90 PS1 l

Model Number: E-;3DH Relative '" **"* ""

Humidity (%) 100% 34 Test 100% D Function: See PZR Heater Contro1 Chemical summary 2400 PPM

> ggg gggggol Spray B ron p

sht. 30A Accuracy:

0.5% Span See Service: Pressurizer Radiation summary 1.5 x 10 8R g level monitoring sht. 30A See

~

Location: Containment Aging P.D.L summary 40 years El. (-)5'-0" sht 30A NA NA Flood Level Elev (-)l4'4" NA A NA Above Flood Level: YesX Suhnergence Mn Notes:

• Documentation

References:

1. Foxboro Test Report Q9-6005

2. MP11 FSAR Table 7.5.2 11-1-80

,T Facility: 7' stone Nuclear Pr. Sta. [

aTION TdORK SHEET [1 Unit: TwoI ,' SYSTEM COMPONENT EM Dockit: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRO!.7.ENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

B2 design see System: Electrical Operating Continuous Continuous 1 Plant ID No.: B52 Time Qualification Box Component: Motor Control Temperature 239 for 56 3.d)

Profile 24 days - 131 2., A.,E. 3.a) Simultaneot s C1.nter (OF) for 96 hrs. Note 1 Test Manufccture: ressure General Electric Co.

See Modal Number: Relative 3 a) Simultaneous summary Humidity (%) 100 99 1 Test sheet Function: Supplies power to Cat. 1 Electrical Chemical NA NA NA NA NA Loads Spray Accurc.cy: Not Required Service: 480V Radiation NA NA NA NA NA Icention: Aux. Bldg. Aging Pl ant 40 yrs. 40 yrs design 3 b) Sequential El. 36' 6" life test Zont A49 Flood Level Elev:

Abova Flood Level: Yes Submergence Mn cDocumentation

References:

Notes:

U The temperature excursion above the test profile is of short

1. Bechtel Spec. 7604-E-7 duration. Based on engineering judgement, NNECO concludes

2. FSAR Amendment 17 that this equipment would satisfactorily perform its safety

3. Wyle Laboratories 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

SIRetARY SHEET NO.

SCEW SHEET NO. 30B n'

D EQUIPMENT ENVIB0lOIENTAL QUALIFICATION M

DISCREPANT EQUIPMENT SIDetARY MILLSTONE UNIT 2 MOTOR CONTROL CENTERS BS2 EQUIPMENT:

MANUFACTURER:

General Electric QUALIFICATION DISCREPANCY:

Subject equipment lacks sufficient qualification documentation with respect to humidity.

fD g SAFETY FUNCTION AND JUSTIFICATION F0h 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 within 60 seconds *after the start of an accident. Based upon engineering judgement, NNECO concludes that the MCC would satisfactorily perform its safety 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 operation 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.

• Except for aux feed valves which presently open,by operator action.

'( -

1

[, 3 Facility: Atone Nuclear Pr. Sta. SYSTEM COMPOUENT E . . ION WORK SHEET ,

Unit: Two Docket: 50-336 1.F* QUAL. OUTSTANDING EINIRO!W.ENT DOCUMENTATION EQUIPMENT DESCRIPTION ~

METHOD ITEMS s

Parameter Spec. Qual. Spec. Qual.

see System: Electrical Operating Continuous Continuous 1 By design Qualification B51, B61 Time box l Plcnt ID No.:

131 for Component: Motor Control Temperature 96 hours A., 2 3 a) Simultaneous C:nt^rs (OF) 112 F max.

Test Manufacture: Pressure l

H H A., 2 H H (PSIA)

Genrral Electric Co. 1 see Mod 1 Eumber: Relative Simultaneous summary ,

Humidity (%) 100 99 1 3 a) test sheet Function: Supplies power to Cat. 1 Electrical Chemical NA NA NA NA NA ads Spray Accuracy: Not Required 480V Radiation NA NA NA Service: NA NA plant Aux. Bldg. Aging Sequential Incetion: 40 yrs 40 yrs design 3 b)

El. 146" life test Zona A24 Flood Level Elev:

Above Flood Level: Yes Suhnergence nn P',tes:

CDocumentation

References:

1. Bechtel Sy c. 7604-E-7

2. FSAR Amendment 17

3. Wyle Laboratories NEQ Test Report 43757-2, September 27, 1978 c) Page X-1 b) Page III-1 31B 11-1-80

8tBSIARY BEEET NO.

31B SCEW SHEET NO. __

m .

ROUIPMENT ElWIROIDtENTAL QUALIFICATION DISCREPANT EQUIPMENT SIRG(ARY MILLSTONE UNIT 2 l

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 :rr 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 coupleted its safety function within 60 seconds after the start of an accident. Based upon engineering judgement, NNECO concludes that the MCC vould satisfactorily perform its safety function since the environmental conditionn 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 equipaent during the time for which its correct operation 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.

p,

([\.,

Facility: s.llstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION ' METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Syctem: Main Steam Operating neous Pln.nt ID No.: PV 4223, Time P Continuous P 1.a) Test PV4224 Simulta-Component: Solenoid Temperature o 324 F Profile neous

( F) Profile Valve 20, A 1.b) Test 10 Pressure Simulta-Manufacture:.ASCO (PSIA) 1.6 psig Profile A 1.b) neous 10 Test Simulta-Mod 31 Number: Relative A neous Humidity (%)

100 1.c)

NP-206-381-6F Test Function: Simulta-Pilot Valve ' Chemical neous Spray

ccuracy

NA N/A B N/A 1.d) Test Saz;vice: Continuous Radiation Sequential

1. 19 #2 Atmospheric Dumps 2x 10 8R N/A 1.e) Test N/A Incation: Aux. Bldg. Aging Req. maint.

EL. 36'6" Sequential performed Zone A50(PV4223) 1 Test every 3 yrs 40 Years 4.4 Years PDL A51(PV4224)

Flood Level Elev:

Abova Flood Level: Yes Submergence Nm 8 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 35-B 11-1-80

.% J Facility: . 11 stone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS MEnI0D Parameter Spec. Qual. Spec. Qual.

See summary System: Main Steam operating Continuous sheet 36Ba Plt.nt ID No.: Time PT.4223, Temperature See summan Component: o sheet Pressure transmitter (OF) 324 F 185 F Profile 1 21, A 36B See summary Hanufactures GE/MAC Pressure sheet 36B (PSIA) 1.6 Psig A See summary Model Number: 551 Relative sheet 36B Humidity (%) 100% 100% A 2 Function: Initiating sig- 1.

nal for steam generator ' Chemical atmospheric dump Spray Accuracy: N/A Service: Steam Radiation Generator Pressure N/A Ince. tion : Aux. Bldg. Aging See summary EL. 36'6"' Zone A50 40 Years P.D.L. sheet 36B Flood Level Elev:

Abova Flood Level: Yes Sulxnergence Mn

' Documentation

References:

Notes:

i

1. GE instruction 198-4532Kil-001A

2. Not affected by exposure to MIL-E-5272 humidity test (24 hr. cycle, 680F to 150 F at 100% relative humidity).

11-1-80 36-B

- - _ . . ~ .. . - . _ _.- - . . _ _ _ . . _ _ _ . . . . - . . -. .- . _- . _ - . _ . - _ .

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Fccility: ( llstone Nuclear Pr. Sta.

' SYSTEM COMPONENT EVALUATION WORK SHEET Units Two- ,

Dockst: 50-336~

~

DOCUMENTATION REF* QUAL. OUTSTANDINC

-EQUIPMENT' DESCRIPTION EINIRONMENT

' ME'nf0D ITEMS Paramete'r Spec. Qual. Spec. Qual. _

See summary System  : Main Steam Operating Continuous sheet Plant ID No.: PT-4224 Time 36B see so - ry Component: Temperature 326 F Profile sheet 36Ba Pressure transmitter FF) 185 F 20, A 1 Manufteture: GE/MAC Pressure sheet 36Ba 1.8 psig A (PSIA)

See summary Model Number: 551 Relative 2 sheet 36Ba Humidity (%) 100% 100% A Function: Initlating sig- F nal for steam generator ' Chemical atmospheric dump SprayN /A Accuracy: ,

Sarvice: Steam Radiation i Generator pressure I N/A j See summary ,

Incation: Aux. Bldg. Aging P.D.L. sheet 36Ba 3 Elev. 36' 6" 40 Years

}

Zone A51 I s

Flood Level Elev: .

f Abova Flood Level: Yes Suisnergence wa l

1. Documentation

References:

Notes:

1. CE instruction 198-4532KIL-001A

2. Not affected by exposure to MIL-E-5272 4

0 humidity test (24 hr. cycle, 68 0F to 150 F I-at 100% relative humidity). i i

I s

36-Ba 11-1-80 N

36B, 36Ba SUtetARY SHEET NO.

36B, 36Ba SCEV SHEET NO.

0 -

EQUIPMENT ENVIP010 ENTAL QUALIFICATION DISCREPANT EQUIPMENT

SUMMARY

MILLSTONE UNIT 2 STEAM CENERATOR PRESSURE TRANSMITTERS EQUIPMENT:

PT-4223, 422i MANUFACTURER: GENERAL ELECTRIC MEASUREMENT AND CONTROLS (GE/MAC)

QUALIFICATION DISCREPANCY:

This equipment is discrepant because it lacks documented qualification test data.

Y SAFETY F N' TION AND JUSTIFICATION FOR CONTINUED OPERATION:

These components provide control loop input for automatic operation of the atmospheric dump valves. This subject was also discussed in the October 5, 1979 letter from W. G. Counsil to 11. R. Denton. To date the staff 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 components there is no effect upon the control room manual operation of the atmospheric dump. Due to the desirability of long term operation of these components they will be replaced with qualified equipment. This replacement will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

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\ ud Facility: tallstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIROtDiENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

4 System: Main Steam operating Continuous See summary Various J Time sheet Plant ID No.:

40B, 40BA Component: Temperature See

( F) 3240 F Profile summary sht

, Solenoid operated valves 21, A '40B, 40BA bee Manufccture: ASCO Pressure summary sht (PSIA) 1.6 psig A 40B, 40BA See Modal Number: Relative summary sht HPX8211B54SW Humidity (%) 100% A 40B, 40BA Function: bee Pilot solenoid valve Chemical summary sht Spray NA N/A 40B, 40BA pcurecy:

See Service: Main steam Radiation summary sht isolation trip valve N/A pilot operator 40B, 40BA See Locntion: Aux. Bldg. Aging P.D.L. summary sht EL. 36'6" 40 Years Zone A50 40B, 40BA Flood Level Elev:

Abova Flood Level: Yes Suhnergence Nn CDocumentation

References:

Notes:

HY-4217 Al HY-4217 B1 HY-4221 Al HY-4221 B1 40-B 11-1-80

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Facility: _llstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 E!NIROmiENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

See System: Main Steam Operating Continuous su= nary sht Plant ID No.: Various Time 40B Component: Solenoid Temperature Profile operated valves (OF) 326 F 8" mary sht 20, A 40B, bee Manufteture: ASCO Pressure summary sht (PSIA) 1.8 psig A 40B, ModJl Number: Relative 100% s m ary sht HT-8211D4 Humidity (%) g 40B, Function: Pilot see solenoid valve ' Chemical Spray summary sht 40B, Accurrcy: N/A N/A See Service: Main steam Radiation summary sht isolation trip valve N/A 40B, pilot operator See Inc-tion: Aux. Bldg. Aging 40 Years P.D.L. summary sht El. 36' 6" 40B, Zone A51 Flood Level Elev:

Abova Flood Level: Yes Suhnergence nn CDocumentation

References:

Notes: HY-4217 A2 HY-4217 B2 HY-4221 A2 HY-4221 B2 40-Ba 11-1-80

SIRetARY SEEET NO. 40B, 40BA SCEW SHEET NO. 40B, 40BA (o

u I

EQUIPMElff ENVIROWEENT)i. QUALIFICATION DISCREFANT EQUIPMENT SUlttARY MILLSTONE UNIT'2 EQUIPMENT:

Solenoid Operated Valves Main Steam Isolation Valve Pilot Operators MANUFACTURER: Automatic Swite.h Company (ASCO)

QUALIFICATION DISCREPANCY: These components are discrepant because they lack documented qualification test data.

SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

These equipments function as pilot operating devices for the main steam isolation valves, (MSIV). The engineered safety features actuation response time for main steam isolation is 6.9 seconds as specified in the technical specifications.

The redundant 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 perfor. nance of this function as described by the existence of the following conditions: l Each MSIV is provided with two separate and redundant vent S0V'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 j 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 f( failure prior to their performing their function within the required time.

v a

bAr t.1 Y runt,11un Anu auss triuu ton ~ ~ . - . . . . ~ . . . . . . , . _..

FOR CONTINUED OPERATION:

SCEW SilEET NO. 40Bu 40BA j The MISV's are reverse acting check valves. llence when a MSIV closure is initiated differential pressure across the MSIV assists in closure of the valve, therefore, reducing the actual closure time to conciderably 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 11. 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 analyzing these components with respect to the accident environment experienced, to establish an operable life for these components under accident conditions. An independent laboratory has been contracted by NUSCO to provide a time / temperature aging analysis for this equipment.

Due to the desirability of long term operation of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicabic, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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Facility: .211 stone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION EINIRONMENT DONMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS

• Parameter Spec. Qual. Spec. Qual.

Safety Injection Simulta-System & . Ctat. Spray Ope {ating neous Plant ID No.: Time P Contiunous P 1.a) Test HY-306 Component: Temperature Simulta-Solenoid valve ( F) 111 F Profile g 1.b) neous 10 Test Manufacture: ASCO Pretssure Simulta-(PSIA) 0.5 psig Profile A, H 1.b) neous 10 Test Model Number: Relative Simulta-A NP-8320A177E Humidity (%) 100% 100 1.c) neous Function: Pilot Test solenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A 1.d). Test N/A B Service: continuous Radiation Sequential 2.2 x 106 R 2 x 108 R K 1.e) Test

, Location: Aux. Bldg. A9109 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 43-B 11-1-80

A g e I (

Facility: ..illstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

1. ~

Systim: Feedwater Operating Plant ID No.: Time HY-5419, P Continuous P 1.a) Test Component: 5421 Temperature 324 F Simulta-Profile Profile neous

( F) 10 21, A 1.b)

Solenoid valve Test Manufacture: ASCO Pressure Simulta-(PSIA) 1.6 psig Profile Note 1 1.b) neous 10 Test Model Number: Relative #~

100s A neous NP-8320A183E Humidity (%) 100 1.c)

Function: Test Pilot solenoid valve ' Chemical Simulta-Spray neous Accuracy: NA N/A B N/A. 1.d) Test S:rvice: Continuous Radiation Sequential N/A 2 x 108 R N/A 1.e) Test Location: Aux. Bldg. Aging Req. maint.

EL. 36'6" Sequential performed Zone A-50 '

40 Yoers 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abova Flood Level: Yes Suhnergence No

• Documentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B 1. The environmental pressure in less than 2 PSIG a) Appendix A Par. 5 b) Appendix A Fig. 9.2 for a duration of 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 46-B 11-1-80

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Facility: ' listone Nuclear Pr. Sta.

' Unit: Two SYSTEM COMPONEFI EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION E!NIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-System: Feedwater Operating ne us Plcnt,ID No.: HY-5420, Time P Continuous' P 1.a) Test 5422 Component: Solenoid Temperature Simulta-

-Valve ( F) 326 F Profile Profile neous 10 20, A. 1.b) Test Manufccture: ASCO Pressure Simulta-(PSIA) 1.8 psig Profile N te 1 neous 10 1.b) Test Mod 31 Number: Relative 100s 100 A 1.c) Simulta-NP-8320A183E Humidity (%) neous Function: Test Pilot solenoid valve Chemical Simulta-Spray neous Ar: curacy: N/A N/A B N/A 1.d) Test S2rvice: 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:

Abova Flood Level: Yes Sutraergence him a

,

• Documentation xeferences: Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B 1. The envircamental pressure is less than a) Appendix A Par. 5 b) Appendix A Fig. 9.2 2 PSIG for about 13 seconds. This is c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 considered insignificant.

c) Appendix D 11-1-80 46 Ba

i .

i Facility: n211 stone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET

- Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Safety Injection Simulta-System: & Ctmt. Spray Operating neous Plant ID No.: Time P Continuour P 1.a) Test HY-657 Component: Temperature Simulta-( F) Profile A neous Solenoid valve 111 p 10 1.b) Test 1 Manufacture: ASCO Pressur 0.5 psig A, H Simulta-(PSIA) Profile neous 10 1.b) Test Model Number: Relative Simulta-A neous NP-8320A177E Humidity (%) 100 1.c)

Function: Pilot solenoid Test valve Chemical Simulta-Spray neous Accuracy: NA NA B NA 1.d) Test Service: Continuous Radiation Sequential 8

2.38x106R 2 x 10 R C,L 1.e) Test Location: 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 Submergence 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

Facility: I O listone Nuclear Pr. Sta, O

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-l Unit: Two SYSTEM COMPOhENT EbwUATION WORK SHEET

- Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTIOf METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

System: S/G Blowdown Operating Sequentia l 4

Plant ID No. : Time Continuous Continuous P 1 Test ZS-4246, 4248 Component: Limit switch Temperature Simulta-( F) 1120F A ne us Profile 7 1.a) Test Manufccture: NAMCO. Pressure Simulta-(PSIA) neous 0.6 psig Profile 7 A,H 1.a) Test Modal Number: Relative Simulta-EA740-20100 Humidity (%) "" ""

100% A Function: Position 100. 1.b) Test Indication & Valve Chemical Simulta-Control Spray neous N/A Accuracy: NA Note 2 NA 1.c) Test Service: S/ 1 wdown Radiation C Sequential

• * " ^" 5 8.41x10 R 2.04x10 8R 1.b) Test Location: Aging 40 yrs. Test & Gasket reple cement Aux. Bldg. 40 yrs. except P.D.L. 2 Analysis required El. (-) 5' 0" Zone A17 easket every 2 yrs.

(? yee_T Flood Level Elev:

Above Flood Level: Yes Subnergence Mn

• Documentation

References:

Notes: 1.This component is subject tc 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 acid, water, sodium c) Page 8 of 12 thiosulfate, and sodium hydroxide, PH between

2. Wyle Report 17436-3 10 & 11 (3000 PPM Baron).

49-B 11-1-80

O t O O Facility: Millstone Nuclear Pr Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

Simulta-System: Main Steam Operating neous Plant ID No.: Time P Continuous P 1.a) Test HY-4246, 4248 Component: Temperature Simulta-pp) 112oF p g Solenoid valve 10 1.b) Test Manufacture: A CO Pressure Simulta-(PSIA) 0.6 psig Profile A, H neous o 10 1.b) Test Model Number: Relative 100% 100 A 1.c) Simulta-Humidity (%) neous NP-831655E Test Function:

Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N.A B N/A 1.d) Test Service: Continuous Radiation Sequential 1.94x106R 2 x 108 R C,L 1.e) Test Location: Aux. Bldg. Aging Req. maint.

EL. (-) 5'0" East Sequential performed Piping penetration room 40 Years 4.4 Years PDL 1 Test every 3 yrs i Flood Level Elev:

Above Flood Level: Yes Subnergence nn

8 Documentation

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 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 50-B 11-1-80

- - _ _ _ _ - -- - - ~ ._ .

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Facility: callstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPCNENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

System: Chem & Volume. Cnt] . Operating Sequential ZS-2525 Time Test Plant ID No.: Continuous Continuous C 1 Component: Limit switch Temperature o Simulta-( F) 112 F A 1.a) neous Profile 7 Test Manufacture: NAMCO Pressure Simulta-(PSIA) 0.6 psig Profile 7 A, H 1.a) neous Test 100 A 1.b) Simulta-Model Number Relative 100%

Humidity (%) neous EA180-ll302 Test Function:

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 8g c,L 1.b) Test Agin9 Test & Gasket replacement Location: Aux. Bldg. 40 yrs.

40 yrs. P.D.L. 2 Analysis required piping penetration room except every 2 yrs.

Zone A-18 gasket (2 yrs)

Flood Level Elev:

Above Flood Level: Yes Suhnergence nn

• Documentation

References:

Notes: 1. This component is subject to a radiation (only) environment.

1. Vendor qual. report, plant file MRIR #1-26-79 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).

51-B 11-1-80

i Facility: rallstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Sy tem: Chem & Volume Cntl Operating neous Plint ID No. : HY-2525 Time P Continuous P 1.a) Test 51multa-Component: Temperature o 112 F Profile A neous Solenoid valve ( F) 10 1.b) Test Manufccture: ASCO Pressure A, H Simulta-0.6 psig (P,SIA) 10 1.b) Test Simulta-Moh l Number: Relative neous NP-8320A18SE Humidity (%) 100% 100 A 1.c)

Test Function:

Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test Sequential S:rvice: Continuous Radiation 1.64x10 R6 2 x 10 8R C,L 1.e) Test Incr. tion : 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:

Abova Flood Level: Yes Subnergence Mn CDocumentation

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. S b) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Per. 9.4.2.4.3 e) Appendix D 52-B 11-1-80

Fccility: rallstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

1. ~

System: RBCCW 7perating Plcnt ID No. : HY-6731 Time P Continuous P 1.a) T Component: Temperature Simulta-Solenoid valve ( F) 111 F Profile A nacus 10 1.b) Test Manufccture: ASCO Pressure Simulta-(PSIA) 0.5 psig Profile A, H neous 10 1.b) Test .

Model Number: Relative Simulta-Humidity (%) 100% 100 A 1.c) neous Function: Test Pilot solenoid valve ' Chemical Simulta-Spray neous Accurrcy: NA N/A B N/A 1.d) Test Service: Continuous Radiation Sequential 8.59x106R 2 x 10 8 R C,L 1.e Test Iccation: 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:

Abov3 Flood Level: Yes Suhnergence nn _

CDocumentation ReferencesL 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 Pa, s.4.2.4.3 e) Appendix D 53-B 11-1-80

O o. v Fccility: w ilstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 m

ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Syctem: RBCCW Operating Sequential Plcnt ID No.: ZS-6731 Time Continuous Continuoua P 1 Test Component: Limit switch Temperature 111 0p Simulta-( F) Profile 7 A 1.a) neous Test Manufacture: NAMCO Pressure Profile 7 A, H 1.d) Simulta-0.5 psig (PSIA) neous Test Simulta-Modal Number: Relative 100 1.b) neous 100% A EA740-20100 Humidity (%) Test Function:

Position Indication ' Chemical Simulta-

& valve control Spray neous Accurccy: NA NA Note 2 NA 1.c) Test Service: Limit switch Radiation Sequential 8.59x106R 2.04x10 8R C,L 1.b) Test Locction: Aux. Bldg. Aging 40 yrs Test & gasket replacement 40 yrs. except P.D.L. 2 Analysis required EL. (-) 45'6" LPSI pump room Zone A2 gasket every 2 yrs .

(2 vrn T Flood Level Elev:

Abova Flood Level: Yes Suhnergence Nn 8 Documentation

References:

Notes: 1. omponent is subject to a radiation Y *"' ""*" *

1. Vendor qual. report, plant file MRIR #1-26-79 2. The spray was composed of boric acid, water, sodium e) Fig. 1, Page 11 of 12 b) Page 4 of 12 thiosulfate, and sodium h). Nxide, PH between c) Page 8 of 12 10 & 11 (3000 M Boron).

2. Wyle Report 17436-3 54-B 11-1-80

FE.cility: Millstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS l

METHOD Parameter Spec. Qual. Spec. Qual.

Syrtem: RBCCW Operating Sequential Plcnt ID No.: ZS-6050 Time Continuous Continuous P 1 Test Component: Limit swtich Temperature o Simulta-( F) 111 F Profile 7 A 1.a) neous Test Manufacture: NAMCO Pressure Simulta-(PSIA) 0.5 psig Profile 7 A, H 1.a) neous Test

1. ~

Mod 1 Number: Relative A . s EA740-20100 Humidity (%)

Function:

Position Indication Chemical Simulta-

& valve. control Spray neous Accuracy: NA NA 'Nte 2 NA 1.c) Test Limit swtich Radiation Sequential Snrvice:

2.9 x 10 5R 2.04x108R C,L 1.b) Test Test & Gasket replz cement Location: Aux. Bldg. T.ging *O yrs.

required EL. (-) 45'6" LPSI 40 yrs. except P.D.L. 2 Analysis gasket every 2 Pump room Zone A2 .

M yea-) yrc.

Flood Level Elev:

Abova Flood Level: Yes Subnergence un CDocumentation

References:

Notes: 1. This component is subject to a radiation

1. Vendor qual report, plant file MRIR #1-76-79 (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).

e 11-1-30

\ 55-B

\

\

Fzcility: Millstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME'n!OD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Sy?; tem: RBCCW Operating neous Plant ID No.: HY-6050 Time P Continuous P 1.a) Test Component: Solenoid Temperature Simulta-vnive ( F) 111 F Profile A 1.b) neous 10 Test Manufacture: ASCO Pressure Simulta-(PSIA) 0.5 psig Profile A, H neous 10 1.b) Test Mod 31 Number: Relative Simulta-NP-8321A6E Humidity (%) 100% 100 A 1.c) neous Test Function:

Pilot solenoid valve Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test S:rvice: Continuous Radiation Sequential 2.9 x 10 5 R 2 x 108 R C,L 1.e) Test Locntion: 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 Flood Level Elev:

Abov?2 Flood Level: Yes Subnergence nn CDocumentation

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 Par. 9.4.2.4.3 e) Appendix D 56-B 11-1-80

Fccility: Millstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPCNEt'T EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Syr. tem : Main Steam operating Sequential Plant ID No.: Time Continuous Continuour P 1 Test ZS-4250, 4251 Component: Limit swtich Temperature Simulta-( F) 112 F Profile 7 A 1.a) neous Test Manufacture: NAMCO Pressure Simulta-(PSIA) 0.6 psig Profile 7 A, H 1.a) neous Test Simulta-Mod 1 Number: Relative neous Humidity (%) 100% 100 A 1.b)

EA180-ll302 Test Function:

Position Indication Chemical Simulta-S valve control Spray neous Accuracy: NA NA Note 2 NA 1.c) Test Service: r.imit switch Radiation Sequential 1.6 10 R 0

2.04x108R C.L 1.b) Test Aux. Bldg. Aging Gasket Incntion: 40 yrs.

EL. (-)5'0" West pipe- 40 yrs, except P.D.L* 2 Test & replacement penetration room Analysis required evt ry gaaket (2y :s . ) , . . _

Zone A18 '~~~

Flood Level Elev:

Above Flood Level: Yes Subnergence na CDocumentation

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 thiosulfate, and sodium hydroxide, PH between 2.* Wyle Report 17436-3 57-B 11-1-80

\s - - - - - - - _ - -

FIcility: tiillstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONEMT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT  ! DOCUMENTATION REF* QUAL. OUTSTANDING i METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Sy~ tem: Main Steam Operating HY-4 250, neous Plcat ID No.: Time 4251 P Continuous P 1.a) Test Component: Temperature Simulta-o Solenoid valve ( F) 112 F Profile A 1.b) neous 10 Test Manufacture: ASCO Pressure Simulta-(PSIA) 0.6 psig Profile A, H neous 10 1.b) Test Model Number: Relative 100% A Humidity (%) 100 1.c) neous NP-8320A185E est Functions Pilot solenoid valve ' Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test S rvice: Continuous Radiation Sequential 1.6 x 106 R 2 x 10 8 R C,L 1.c) Test Inc; tion: Aux. Bldg. Aging -

i Req. maint.

EL. (-)5'0" West pipe- Sequential performed pen tration rocxn -40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-18 Flood Level Elev:

Abova Flood Level: Yes Sulxnergence Mn CDocumentation

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 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 58-B 11-1-80

~-

('

3-i Fzcility: aallstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Dockst: 50-336 ENVIP.ONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

See Summary Sy; tem: Main Steam Operating Continuous sheet Pirnt ID No.: HY-4209, Time 66B, 66Ba Temperature See summary Component: Profile Solcnoid operated valve ( F) 326 F 20, A 66B. 66Ba See summary Manuf acture : ASCO Pressure sheet (PSIA) 1.8 psig A 66B, 66Ba Relative 3ee sn e ry Mod 31 Number: A WPHTX-8320A184 Humidity (%) 100% sheet

$6B, 66Ba Function: see summary Pilot solenoid valve ' Chemical i Spray sheet NA NA 56B, 66Ba Accurccy: NA Radiation see su= mary Service: Main Steam sheet Hrder Low Point Drains '66B', 66Ba Aux. Pldg. Aging See summary Locntion:

EL. 36'6" 40 yrs. P.D.L. sheet EL. 14'6" Zone A51 56B, 66Ba Flood Level Elev Abova Flood Level: Yes Suhnergence nn CDocumentation

References:

Noter:

66-B 11-1-80

StatlARY SEEET NO. 66B.

SCEW SHEET NO. 66Bs EQUIPMENT ENVIBOSIENTAL QUALIFICATI DISCRIPANT EQUIPMENT SIRetARY MILLSTONE UNIT 2 EQUIPMENT: SOLENOID OPERATED VALVE PILOT OPERATOR FOR MAIN STEAM HEADER LOW POINT DRAINS HY-4209, 4193 Automatic Switch Company (ASCO)

MANUFACTURF.R.

QUALIFICATION DISCREPANCY:

These components are discrepant because of the lack of documented qualification data.

Ov SAFETY FUNCTION AND JUSTIFICATION 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, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date. An independent laboratory has been retained by NUSCO to provide time / temperature aging analysis for this equipment.

O-

-"w Facility: _llctone Nuclear Pr. Sta.

Unit Two ,

SYSTEM COMPONENT EVALUATION WORK SHEET Doclot: 50-336 ENVIPDNMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

Main Steam See Simmary Sy tem: Operating Continuous Time Sheet Plant ID No.: HY-4193 66Ba Temperature See summary Ccaponent:

( F) Profile sheet Solenoid operated valve 324 F 21, A 66Ba Manufactue: ASCO Pressure 1.6 psig A See summar)

(PSIA) sheet 66Rn See summary Model Number: Relative 100% A sheet WPHTX-8320A184 Humidity (%)

66Ba Function:

Pilot solenoid valve ' Chemical See summary sheet Spray NA NA 66Ba Accuracy: N/A Main Steam See summary Service- Radiation Hender hw Point Drains sheet 66Ba See summary Icc2 tion: Aux. Bldg. Aging 40 yrs. P.D.L. sheet El. 36' 6" 66Ba Zone A50 Flood Level Elev:

Abov3 Flood Level: Yes Sulnargence

- I CDocumentation

References:

Notes:

66-Ba 11-1-80

SIMIART SERET NO. 66Ba SCEW SHEIT NO. 66Ba n a

~

b' EQUIPMENT INVIBOIStElriAL QUALIFICATION DISCEEPANT BQUIPMiDIT SinMART MILLSTONE UNIT 2 EQUIPMENT: SOLENOID OPERATED VALVE PILOT OPERATOR FOR MAIN STEAM HEADER LOW POINT DRAINS HY-4209, 4193 MANUFACTURER:

Automatic Switch Company (ASCO)

QUALIFICATION DISCREPANCY: These components are discrepant because of the lack of documented qualification data.

SAFETY FUNCTION AND JUSTIFICATION 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 componenta to perform this function is bounded by the existing accident analysis.

Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that, procurement delays do not preclude replacement by that date. An independent laboratory has been retained by NUSCO to provide time / temperature aging analysis for this equipment.

0;  ;

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Facility: .allstone Nuclear Pr Sta.

I Unit: Two SYSTEM COMPONENT EVALUATION WORK SH M Dockst: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAR.. OUTSTANDING HETiiOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simultaneou.;

System: RBCCW Operating Continuous Continuous P 1, 2 Test Plant ID No.: Time PS-6119 A, B, C Component: Temperature Simultaneou a Prntsure switch (OF) 110 F 160 F A 1,2 Test Manufacture: Pressure Custom Component 0.4 psig 16.0 psia A, H 1, 2 Simultaneou  ;

(PSIA)

Test 1, 2 Model Number: Relative 604-GBR2-352 S Humidity (%) 100% 100% A Simultaneou a Test Function:

Valve control circuit ' Chemical Spray Accuracy: N/A NA NA Service: Continuous Radiation N/A Inc; tion: Aux. Bldg. Aging See su e ry sht 40 Years EL. (-)25'6" P.D.L.

Zona A1B 67B Flood Level Elev:

Abovs Flood Level: Yes Sulraergence nn CDocumentation

References:

Notes:

1. 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

o.'S .

"'"* StmetART SEEET NO. 67B SCEW SHEET NO. 67B o .

EQUIPMENT INTIRol0GNTAL QUALIFICATION DISCRIPANT-EQUIPMENT SIDMARY MILLSTONE UNIT 2 EQUIPMENTi Pressure Switches PS-6119, A, B, C MANUFACTURER: Custom Component Switches (CCS)

QUALIFICATION. DISCREPANCY: These components lack documented radiation and time / temperature aging qualification date-SAFETY FONCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

These components provide low suction header pressure protection for the reactor building closed cooling water pumps.

An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Due to the present age of this equipment, the results of the 3 ng 1 analysis are not critical to establish reasonable assurance that the equipment will perform its function.

Fccility: 'rallstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50 '36 EQUIPMENT DESCRIPTION ENVIROtD".ENT doc M 1TATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Gas & Aerated Simulta-Sy tem: Liquid Radwaste W rating P Continuous P 1.a) neous Plant ID No.: Time Test HY-9126, Component: Temperature Simulta-o Solcnoid valve ( F) 112 F Profile A 1.b) neous 10 Test Mantifacture : ASCO Pressure (PSIA) 0.6 psig Profile A, H 1.b) Simulta-10 neous Test Mod 21 Number: Relative Simulta-100% 100 A 1.c) neous NP-8321A5E Humidity (%)

Function: Test Pilot solenoid valve ~ Chemical Simulta-Spray neous Accuracy: NA N/A B N/A 1.d) Test Service: Radiation 1 Sequential continuous 1,9 x 19 6R 2 x 108 R C,L 1.e) Test Locntion: Aux. Bldg. Aging Req. maint.

EL. (-) 5'0" West pipe Sequential performed pen-tration room 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abova Flood Level: Yes Subnergence na CDocumentation

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.?

c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 e) Appendix D 68-B 11-1-80

^

O f Facility: .llttone Nuclear Pr. Sta.

Unit Two ,

SYSTEM COMPONENT EVAIVATION WORK SHEET Dock:t: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.

Gas & Aerated Simulta-Sy;; tem: Liquid Radwarte Operating neous Plant ID No.: Time P Continuous P 1.a) Test HY-7690  ;

Component: Temperature Simulta-( F) Profile A neous Solenoid valve 112 F 10 1.b) Test .

Manufacture: ASCO Pressure Simulta- ,

(PSIA) 0.6 psig Profile A, H neous 10 1.b) Test f' Simulta-Model Number: Relative NP-8320A189E Humidity (%) 100% 100 A 1.c) ner.us Test Function:

Pilot Solenoid valve ' Chemical Simulta-Spray neous Accuracy: F/A N/A B N/A 1.d) Test Service: Continuous Radiation Sequential 1.9 x 10 6 R 2 x 10 8 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint.

El. (-) 5' 0" Sequential performed 40 Years 4.4 Years PDL 1 Test every 3 yrs ,

Flood Level Elev:

Above Flood Level: Yes Subnergence cDocumentation

References:

Notes: 1. This component must function in a radiat. ion (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 68-Ba 11-1-80

Fccility . llstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docktt: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

See summary Gas & Aerated Sy; tem: Liquid Radwaste Operating Continuous sheet Plent ID No.: Time 69B ZS-9126, Component: Temperature See summary Limit Switch ( F) 112 F A sheet 69B See stimary Manufccture: NAMCO Pressure (PSIA) sheet 0.6 psig A, H 69B Mod]l Number: SL3CB2 Relative A See sumary 100%

Humidity (%) sheet Function: Valve position 69B

' chemical See summary indication & control Spray 8 **

circuitry NA NA Accurrcy:NA 69B 5ee mi "n ry Service: Waste Gas tank Radiation sheet

~

inlet isolation valve 1.94x106R C,L 69B Loc 2 tion: Aux. Bldg. Aging See summary sheet EL. (-) 5'0" West pipe P.D.L.

40 Years , 69B penetration room Zone A17 Flood Level slev:

Abova Flood Level: Yes Subnergence Nn CDocumentation

References:

Notes: This component must function in a radiation (only) environment.

69-B 11-1-80

lit '

C  : StatfARY SEEET HO. 69B SCEW-SEEET NO. 69B n .

EQUIPMENT INTIMOISIENTAL QUALIFICATION )

DISCRIPANT 3QUIPMENT SIDS(ARY MILLSTONE UNIT 2 EyutreiENT:' STEM MOUNTED LIMIT SWITCH ZD-9126 Ex-Containment Gas & Aerated Liquid Radwaste Containment Isolation Valve MANUFACTURER: (NAMCO) - National Acme Corporation QUALIFICATION DISCREPANCY: This equipment lacks documented qualification data.

O

'Q< 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 position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon.as practible, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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I Fccility: _ll::tonn Nuclear Pr. Sta.

Unir.: Two ,

SYSTEM COMPONENT EVALUATION WORK SHEET Dock,t: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD It.' EMS I Parameter Spec. Qual. Spec. Qual.

Gas & Aerated See Sy; tem: Liquid Radwaste Operatin9 Continuous summary Plant ID No.: Time sheet ZS-7690 69Ba Cmponent: Temperature See Lilit Switch A suma ry (OF) 112 F sheet 69Ba Manufacture: NAMCO Pressure See sumary (PSIA) 0.6 psig A, H sheet 69Ba See sumary  !

Mod 31 Number: SL3CB2 Relative Humidity (%) sheet j Function: valve position 69Ba  !

indication & control " Chemical See summary circuitry Spray sheet .

Accuracy: N/A NA NA 69Ba See sumary i S*rvice: Reactor coolant Radiation sheet cemple valve 1.64x106R C,L 69Ba f, Ioc tion: Aux. Bldg. Aging See summary l El. (-) 5' 0" 40 Years P.D.L. sheet 3 Zone A18 69Ba l I

Flood Level Elev:

Abova Flood Level: Yes Subnergence ,

na CDocumentation

References:

Notes:

This cmponent must function in a radiation (only) environment.

4 t

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4

-Ba 11-1180 $'

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.T. 4. i 1 J .:'

chp ggggGJtYtSHIET NO. 69Ba. _

SCEW SHIET NO. 69Ba 6

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EQ N ENVIROWIINTAL, QUALIFICATION DISCIEPAltf EQUIPMDrr SUntARY

> 6 MILLSTONE UNIT 2 EQUIPtWNT: . STEAM MOUNTED LIMIT. SWITCHES ZS-7890 Gaseous & Aerated Liquid Radwaste Ex-Cont &inment Isolation Valve MANUFACTURER: National Acme Corporation (NAMCO)

QUALIFICATION DISCREFANCY: These components lack documented qualification data.

h' SAFETY FUNCTION AND JUSTIFICATION FOR CONTIN N OPERATIONt 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 positi n indication operability of this equipment, it will be replaced with. qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delaya do not preclude replacement by that date.

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.J FCcility: ' Millstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Dockst: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ME790D ITEMS Parameter Spec. Qual. Spec. Qual.

See.snemry Sy; tem: Service Water Operating Continuous sheet 70B Plant ID No.: 6307B Time TY-6308, 6307A, 6306 Component: Temperature See summary 110 F Solenoid valve ( F) A sheet 70B ASCO see summary Manufteture: Pressure (PSIA) 0.4 psig A, H sheet 70B See sumury Mods 1 Number: Relative Iumidity(%) 100% A sheet 70B HT-8320A-102 Function: ,

Pilot solenoid valve Chemical Spray See summary Accuracy: NA NA NA sheet 70B See summary Service: Radiation RBCCW Heat Exchanger N/A sheet 70B Incntion: Aux. Bldg- Aging See summary EL. (-)25'6" 40 Years P.D.L. sheet 70B Zone AlB _

Flood Level Elev:

Abova Flood Level: Yes Subnergence Mn .

CDocumentation

References:

Notes:

70-B 11-1-80

SIDelARY SEEET NO.

SCEW SHEET NO.

(O

\d~ EQUIPMENT ENVIROIOGNTAL QUALIFICATION DISCREPANT EQUIPMENT SUlt(ARY MILLSTONE UNIT 2 i SOLENOID OPERATED VALVES EQUIPMENT: Pilot operating valves for IIU-6306, 6307A, 6307B, 6308 FACE RER:

Automatic Switch Company (ASCO)

QUALIFICATION DISCREPANCY: These components are discrepant because they lack documented qualification data, q

Q SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

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 environment will not impair'these components in the performance of their safety function. The manufacturer 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, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

l l

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O a Facility: milstone Nuclear Pr. Sta.

. Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.  ;

See summary ',-.

Sy2 tem: Service Water Operating Continuous sheet 71B

' PlEnt ID No.: Time ZS-6306, 6307, 6308 Component: Temperature See sumary (op) A sheet 71B Limit Switch 110 F See sumary Manufccture: NAMCO Pressure 0.4 psig A, H sheet 71B (PSIA)

Relative See summary Mod:el Number: D-2400X 100% A Humidity (%) sheet 71B Function: Position Chemical See summary Indication & Control sheet 71B Circuit Spray NA NA Accuracy: NA r

see sumary Radiation sheet 71B Service: Limit switch NA Aging See summary Location: Aux'. Bldg.

40 Years P.D.L. sheet 71B EL. (-)25'6" Zone AlB Flood Ievel Elev:

Abova Flood Level: Yes Subnergence e

8 Documentation

References:

Notes:

11-1-80 4

SUle(ARY SHEET NO. 71B SCEW SHEET NO. 71B  !

o -

EQU1PMENT ENVIRONMENTAL QUALIFICATION

\

l DISCREPANT EQUIPMENT SUtefARY 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)

QUALIFICATION DISCREPANCY:

SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATIOU*

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 outnide the containment and are subject to an environment which is enveloped by the equipment catalog specifications.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Due to the desirability of long term position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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Facility: .u11 stone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Close & stay See summary System: Service Water Operating closed on sheet 72B Plcnt ID No.: Time SIAS & SLB HY-6438, 6439 outside ent nt.

Temperature See summary Component: ' fi 4 way solenoid valve (oF) 155 F sheet 72B 22, A See sumary Manufacture: ASCO Pressure sheet 72B (PSIA) 0.5 psig A, H See sumary Modil Number: Relative 100% A sheet 72B HT-834481 Ilumidity (%)

Function: '

See summary Pilot solenoid valve Chemical NA NA NA Accuracy:

See sumary Service: TBCCW HX inlet Radiation sheet 72B isolation NA Location: Turbine Bldg. Aging See summary EL. 14'6" P.D.L, sheet 72B 40 Years Zone T10 _.

Flood Level Elev:

Above Flood Level: Yes Subnergence Mn CDocumentation

References:

Notes:

72-B 11-1-80

72B SUlelARY SHEET NO.

72B SCEW SHEET NO.

C EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SIDefARY MILLSTONE UNIT 2 SOLEN 0ID OPERATED VALVES EQUIPMENT:

Pilot Operators for Valve No. (IIV-6438, 6439)

1. 1, 2 & 3 turbine building closed cooling water heat exchanger inlet isolation valves MANUFACTURER:

Automatic Switch Company (ASCO)

QUALIFICATION DISCREPANCY: .These components lack documented qualification data.

SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

These components function as pilot operating mechanisms for TBCCW valves outside containment. 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 tc the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30 1982, assuming that procurement delays do not preclude replacement by that date.

An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

O.,

- - - . ~ . - -. ~ .- . . . . , . - - - ._ . - - -..- _ . - - -- . _ . _ . . .. - - _ . .

Facility: milstone Nuclear Pr. Sta.

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two

, Dockat: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT

, EQUIPMENT DESCRIPTION MEM OD ITEMS Parameter Spec. Qual. Spec. Qual.

Intermit- sequential Sy", ten:SI.& CNTMT SPRAY Operating Note 1. tent-30 min Note 1 1.a) test Plant ID No.: Time HV3008, HV3009 cbcbesfor s.

j Component:' Valve Motor Temperature Operators (OF)

NA

. Manufacture Pressure ,

Limitorque (PSIA)

NA r

Model Number: Operator Relative S/N 152444, 152443 Humidity (%)

Function: Operators NA For CS 16.lA, 16.lB " Chemical Spray Accuracy: Not required NA Service: Containment sumjl Radiation sequential 8 2.a) test recirculation 8.6 x 10 6R 2.04x10 R' C,L Aging plant Incation: Aux. bldg.

Zone A2 simulated design 1.b) sequential el'. (-)45'6" 40 Yrs. 40 yrs. life test Flood Level Elev:

l, Above F~ood. Level: Yes Sulunergence un

• Documentation

References:

Notes:

l. Limitorque Test Report 600198 1/2/69 to 4/29/69 1. Valve must open on SRAS and stay open under radiation and Addemdum 1 (only) environment. Ref . FS AR 6.2.3.1, sys. description.

a) page 4

-i . b) page 5 l

2. Limitorque Test Report 600376A,4/26/76 to 8/30/72 a) Par. 2.1 83-B 11-1-80  ;

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Facility: Millstone Nuclear Pr. Sta.

SYSTEM COMPONENT EVALUATION WORK SHEET Unit: Two Dockst: 50-336 QUAL. OUTSTANDING ENVIRONMENT DOCUMENTATION REF*

EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

1.a) sequential Sy tem Chem. & Vol. Cntl Operating 200 Note 1. test Plant ID No.: CH 501 Time cycles Note 2 Component: Valve Motor Temperature Operator ( F)

NA Manufccture: Limitorque Pressure (PSIA)

NA Model Number: Operator Relative S/N 134086 Humidity (%)

Function: Operator NA for CH501 Chemical Spray Accuracy: Not required NA Radiation 8 1.b) sequential Service Volume control 8.32x105R 2.04x10 R C,L tank discharge valve test W ; tion: Aux. Bldg. Agin9 simulated plant E1 (-)25'6" Zone A9 40 yrs. 40 yrs, design 1.c) sequential life test Flood Level Elev:

Abova Flood Level: Yes Subnergence un Notes:

CDocumentation

References:

1. Limitorque Test Report B0003 11/13/74 to 1/23/75 1. Valve must close and stay closed under radiation 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 84-B 11-1-80 I

- ~ . . - .. - . - . . . . .-. - -

Ftcility:' w ilstone Nuclear Pr. Sta,

(^

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Unit: SYSTEM COMPONENT UATION WORK SHEET - {~-

Dockst: v-336 4

ENVIRONMENT Note 3. DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMEN'" DESCRIPTION ITEMS METHOD-

~

Parameter Spec. Qual. Spec. Qual. _

System: 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 py)

NA

' - Manufacture Westinghouse Pressure (PSIA)

NA

, Model Number Cat. Type Relative TCDP Humidity (%)

Yunction: Pump Drive NA

' Chemical Spray Accuracy: Not required a NA i' Service: Charging Pumps Radiation 5 8 sequential 5.25x10 R 2x10 R C,L 2.a) test I m tion: Aux. Bldg. Aging sequential El. (-) 25 ' 6" Zone A9 40 yrs. 40 yrs. 1. 2.b) test Flood Level Eleva Above Flood Imvel Yes Suhmargence un

• Documentation

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 early 1981.

4

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 must function in a 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 11-1-80

l

,f' l

l'"

I l Facility: Millstone Nuclear Pr. Sta.

Unit: *Two SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION MEnf0D ITEMS Parameter Spec. Qual. Spec. Qual.

continuous 1, 2

' System Chem. & Vol. Cntl. Operating continuous Plant ID No.: PS224X, Time PS224Y, PS224Z Component: Temperature Vacuum switches (OF) 110 F 160 F A 1, 2 Manufccture: Custom Pressure Component (PSIA) '

0.4 PSIG A,H Model Number: Relative

• 604 VBI-351S Humidity (%) 100 A -

Function: Valve / pump control Chemical Spray Accurrcy:

NA NA Service : P18A,B,C Radiation suction header See summary Incntion: Aux. Bldg. Aging sheet 86B 40 Years P.D.L.

El. (-) 25 ' 6" Zone AlB Flood Level Elev:

Above Flood Level: Yes Subnergence un CDoctamentation

References:

Notes:

1. 10-13-80 letter from Theryn Eckstein, Custom Control Sensors, to R. K. McCarthy

2. Custom Component Switches Test Report QTR 604-01 11-1-80

- - _ _ _ _ ___[_ ._

!! S .*

O~ staedARY SEEIT NO. 8:B 86B SCEV SERIT NO.

BQUIPMEND ENVIBSIMENTAti QUALIFICATION

=DISCREFANT EQUIPMENT'SIDMARY MI14.830NE 12 TIT 2 Pressure Switches PS-224X, Y, Z EQUIPMENT!

. Charging Pump Suction Header Pressure MANITFACTURER 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 prot:ection for the charging pumps.

An independent laboratory has been contracted by NUSC) to provide radiation and time / temperature aging analysis ,for this equipment.

Due to the present age of this equipment, the results of the aging analysis are not critical to establish reasonable assurance that the equipment will perform its function.

O, s

pm F;cility: ru.llstone Nuclear Pr. Sta.

Unit: Two SYSTEM COMPONENT EVALUATION WORK SHEET Dockst: 50-336 ENVIRONMENT Note 2. DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS MEDIOD Parameter Spec. Qual. Spec. Qual.

Intermit-System: SIS & Cont. Spray Operating tent-30 min Note 3. 1.a) se ve # al Npte 1. test Plcnt ID No.: HV3021 Time cycles for 9 hrs.

HV3022 Component: Valve Motor Temperature Operator ( F)

NA Manufacture: Limitorque Pressure (PSIA)

NA Mod 31 Number: Operator Relative S/N 145931 Humidity (%)

NA Function: Operator for CS 4.lA ~ Chemical Accuracy: Not required A S;rvice: Cont. Spray Radiation sequential 6 8 Stop' valve 2.57x10 R 2.04x10 R c,L 2.a) test Locntion: Aux. Bldg. Aging simulated plant El . (-) 5 ' 0" Zone A18 40 yrs. design 1.b) sequential 40 Yrs. test (HV3021), A17(HV3022) life Flood Level Elev:

Abova Flood Level: Yes .

Subnergence m I cDocumentation

References:

Notes:

1. Valve must open and stay open. May require to 1 T.imitorque Test Report 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) anvironment.

a) page 4 3. FSAR 6.4.3.1 & P & ID 25203-26017 b) page 5

2. Limitorque Test Report 600376A,4/26/72 to 8/30/72 a) Par. 2.1 11-1-80 89-B

~

- l .--

Facility: . alls;tona Nuclc .r Pr. Sta.

Unit: Two ,

SYSTEM COMPONENT EVALUATION WORK SHEET Dockct: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

See sumary Syltem: Cntmt. Press. Operating continuous 2 sheet 91B Plant ID No.: PT-8113, Time 8114, 8115, 8116 Component: Temperature See sumary Prras. Transmitter (OF) A sheet 91B 112oF Manufacture: Foxboro Pressure See sumary (PSIA) sheet 91B 0.6 PSIG A,Il See sumary Model' Number: Relative E-llDM Humidity (%) sheet 91B 100% A Function:

' Chemical see summary Spray sheet 91B Accuracy: NA NA

" " 7 Service: Cntmt. Press. Radiation Sequential sheet 91B 2.22x106R 1x 10 7R C 1 Test Aux. Bldg. Aging See sumary Iocati El. f 5' 10" A17,A18 40 Years P.D.L.

sheet 91B Flood Level Elev:

Abova Flood Level: Yes Subnergence na

" 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

~

s.t. 91B

[f S N SEEllT^NO.

SCEW SHEET NO.

I

• EQUIMWff'ENVIBI($5NTAIt<QtiA1.1FICATION I

) "DISCRESANT}BQUIBSNT'SU39tARY 1 N41tPItBE' UNIT 2 Containment Pressure Transmitters PT-8113, 8114, 8115, 8116

.EQUN:

M ACTURER: Foxboro.Model Ell-DM These components lack documented qualifications QUALIFICATION DISCREPANCY: concerning radiation and time / temperature aging, SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

This equipment provides signal input for engineered safety features act uation of the containment spray, enclosure building filtration, containment isolation and amergency core cooling systems on.a high containment pressure condition.

The catalog specifications for this equipment envelop the environmental parameters experienced by these-.componente during the accident, therefore, the environment will not impair these components in performance of their safety function. An independent laboratory has been contracted by NUSCO to provide a radiation and time / temperature aging analysis for this equipment.

The capability for long term monitor ng of containment pressure will be verified upon receipt of the radiation and time / temperature aging analysis.

Also, two additional environmentally qualified channels of containment pressure monitoring have been installed'for post accident monitoring.

Due to the present age of this_ equipment, the results of the aging analysis are not critical to establish reasonable assurance that the equipment will perform its function.

I l

^

~

9 _.

Facility llCton3 Nuclear Pr. Sta.

Unit: Two , SYSTEM COMPONENT EVALUATION WORK SHEET Dockat: 50-336 i

EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING MEnlOD ITEMS Parameter Sp6c. Qual. Spec. Qual.

System: Safety Injection Operating Simulta-Plant ID No.: Time neous HY-306 P Continuous P 1.a) Test nen Temperature Simulta-gcnoig:operatedvalve goF) Profile neous lll'F 10 A 1.b) Test Manufccturei ASCO Pressure Simulta-(PSIA) Profile . neous 0.5 PSIG 10 A,H 1.b) Test Model Number: Relative Simulta-NP-8320A177E Humidity (%) neous Function: Pilot valve 100 100 A 1.c) Test

' Chemical Simulta-Spray neous Accurrcy: N/A N/A B N/A 1.d) Test Service: Shutdown cooling Radiation 2.29 x 6 10 Sequential Flow control bypass Rads x 108 R C,L 1.c) Test Incntion: Aux. Bldg. Aging Req. maint.

El. (-) 45 ' 6" Sequential performed Zone A-2 '40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abovo Flood Ievel: Yes Subnergence un CDocumentation

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) Apperdix D 92-B 11-1-80

___________ _----- .- m

Fccilitys llaton'a Nuclear Pr. Sta.

Unit Two , SYSTEM COMPONENT EVALUATION WORK SHEET Docht: 50-336 EQUIPMENT DESCRIPTION E!NIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

^~

System: Safety injection Operating ne us Plant ID No.: Time Test HY-659, HY-660 P Continuous P 1.a)

Components . len id Temperature Simulta- i

-operated valve (oF) Profile neous ,

N/A 10 N/A 1.b) Test '

Manufacture: ASCO Pressure Simulta-(PSIA) Profile neous j N/A 10 N/A 1.b) Test '

Model Nucber: Relative Simulta-NP'-831655E Humidity (%) neous Function: Pilot solenoid N/A 100 N/A 1.c) Test valve ' chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Service: Safety injection r.distion Sequential Pump discharge bypass 6.37x106R 2 x 10 8 R C,L 1.e) Test h nder Inc tion: Aux. Bldg. Aging Req. maint.

El. (-) 45 ' 6" Sequential performed

'40 Years 4.4 Years PDL 1 Teet every 3 yrs ,

Flood Level Elev:

A% va Flood Level: Yes Suhnergence I

• CDocumentation

References:

Notes: This component is subject to a

1. ASCO Test Report No. AQS 21678/TR Rev. B radiation only environment.

c) 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 94-B 11-1-80

f m i

',,m,e Facility: llctona Nuclear Pr. Sts. -

Unit: Two ,

SY3 TEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUlPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS  !

Parameter Spec. Qual. Spec. Qual.

Primary Makeup Simulta-System: Water Operating s Plant ID No.: HY-7311 Time P Continuous P 1.a) Test component: Solenoid Temperature Simulta-operated 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 +

Simulta- I Model Number: Relative NP-8321A5E Humidity (%) neous ,-

Function: Pilot solenoi.d 100 100 A 1.c) Test i vrive ' Chemical Simulta-Spray neous a AccurEcy: N/A N/A B N/A 1.d) Test Service: Primary makeup Radiation Sequential water to quench tank 2 x 108 R 1.94x106R C,L 1.e) Test l' t

Location: Aux. Bldg. Aging Req. maint. 3 El. (-) 5' 0" Sequential perforr.ed {

Z:ne A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs l

i Flood Level Elev:

'Qxwa Flood Level: Yes Suhnergence CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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  !

i 1

1 95-B 11-1-80 4

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\

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Facility: ..lletons Nuclonr Pr. Sta. -

Unit Two , SYSTFM COMPONENT EVALUATION WORK SHEET Dockr.t: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-System: Recirculation Operating Plant ID No.: HY-6073, Time P Continuous P 1.a) 6077 Component: Solenoid Temperature Simulta-v21ve (DF) Profile neous 112*F 10 A 1.b) Test Manuf:cture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Simulta-Mod 21 Number: Relative NP-831655E Humidity (%)

Function: 100 100 A 1.c) Te Pilot solenoid valve ' Chemical Simulta-Spray neous Accur cy: N/A N/A B N/A 1.d) Test Service: Ctmt. air recirc Radiation Sequential cooled inlet 2.42x106R 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 Le/el Elev:

Abova Flood Level: Yes Suhnergence Mn CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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 96-D 11-1-80

Fr_cility : milctone Nuclear Pr. Sta.

Unit: Two , SYSTEM COMPONENT EVALUATION WORK SHEET Dock;t: 50-336 EQUIPMENT DESCRIPTION E!NIRO1 DENT DOCUMENTATION REF* QUAL. OUTSTANDING ME'DIOD ITEMS Parameter Spec. Qual. Spec. Qual.

Cntmt. Air Recirc Operating Simulta-Sy;tems Plant ID No.: HY-6084, neous Time 6092 P Continuous P 1.a) Test Cocponent: Solenoid Valve ' Temperature Simulta-( F) Profile neous 112*F 10 A 1.b) Test ASCO Manufuctura: Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Mod;l Number: Relative Simulta-NP-831655E Humidity (%) ncous Function: Pilot solenoid 100 100 A 1.c) Test

1. 21V# ~ Chemical Simulta-Spray neous Accuracy: N/A N/A B N/A 1.d) Test Servic3: Ctmt. air recirc Radiation Sequential 0

cooler control valve 2.56x106R 2 x 10 R C,L 1.e) Test Locnti'an 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 Ievel Elev:

Abova Flood Level: Yes Subnergence un CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B e) Appendix A Par. 5 ) Appendix A Fig. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 c) Appendix D 97-B 11-1-80

O O O Facility: _llatone Nuclear Pr. Sta.

Unit Two , SYSTEM COMPONENT EVALUATION WORK SHEET Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OtfrSTANDING METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Sample & Gas Syatem 3 ,

Effluents Operating Plant ID No.: HY-6092 Th P Continuous P 1.a) Te Component: Solenoid Temperature simulta-operated valves ( F) Profile neous 112,F 10 A 1.b) Test Manufccture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Model Number: Relative Simulta-NP-831655E Humidity (t) neous Function: Pilot solenoid 100 100 A 1.c) Test valva ' Chemical Simulta-Spray neous Accurtcy: N/A N/A. B N/A 1.d) Test Servica: Sample & Gas 1.02X106R 2 x 10 8 R C,L 1.e) Sequential

~

Radiaticn cffluInt filter stop Test valva Iocation: Aux. Bldg. Agin9 Req. maint.

El. (-) S' 0" Sequential performed Zone A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abova Flood Level: Yes Subnergence un CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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 98-B 11-1-80

O .O a Facility: listona Nuclear Pr. Stc.

Unit - Two- SYSTEM COMPONENT EVALUATION WORK SHEET  !

4 lDockat: 50-336 1

' EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING ME1 HOD . ITEMS Parameter Spec. Qual. Spec. Qual.

Instrument Air Simulta-Sy;tes: Operating Plant ID No.: HY-7083 Th P Continuous P 1.a)

Component: Temperature Simulta-( F) Profile neous j Solenoid operated valve ll2*F 10 A 1.b) Test a Manufacture: ASCO Pressure Simulta- I (PSIA) Profile neous i 0.6 PSIG 10 A,H 1.b) Test i Model Ni=har Relative Simulta-NP-8321ASE Humidity (t) neous Function: Pilot valve 100 100 .A 1.c) Test'-

" Chemical Simulta-Spray neous Accurtcy: N/A' N/A B' N/A 1.d) Test Servica: Ctat. instrumenq Radiation Sequential air block valve 6. 8 1.65x10 R 2 x 10 R. C,L 1.e) Test Iccation: 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 Imvel Elev:

Abova Flood Imvel: Yes Suhnergence un 1

• Documentation

References:

Notes:

I

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

. - - _ - . _ _ . _ . _ - . _ _ . - _ - - - _ _ _- - - w + + = - ------~~1 --- . _ - _ - - - _ - - - -

m ,,

Fccility: _ll::; tone Nucir.r Pr. Sta.

Unit Two ,

SYSTEM COMPCNENT EVALUATION WORK SHEET Dock;t: 50-336 ,

ENVIRONMENT DOCUMENTATION REF* QUAL. O(JfSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Sy~tema Primary Drain Operating neous Plant ID No.: HY-9016 Time Continuous P 1.a) Test P ,

Simulta- f Component: Solenoid Temperature operated valves ( F) Profile neous l ll2* F 10 A 1.b) Test 1 Manufzeture: ASCO Pressure Simulta- .

(PSIA) Profile neous f 0.6 PSIG 10 A,H 1.c) Test s Simulta-Mod 31 Number: Eelative neous NP-8321A5E Humidity (%)

Functirn: Pilot valve 100 100 A 1.d) Test

~ Chemical Simulta-Spray neous l

/Accurtcy: N/A r;/A B N/A 1.d) Test

. Servica: Primary drain Radiation Sequential tank discharge isol. 2.12x106R 2 x 108 R C,L 1.e) Test valvo Inc2 tion: Aux. Bldg. Aging Req. maint.

El. (-) 5' 0" Sequential performed 40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-18 ,

Flood Level Elev:

Abova Flood Level: Yes Suhnergence nn CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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 100-B 11-1-80

(~h (m ,

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Facility: m_llitone Nuclear Pr. Stc. ..

Unit: Two ,

SYSTEM COMPONENT EVALUATION WORK SHEET Doclot: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHCD ITEMS Parameter Spec. Qual. Spec. Qual.

RCS Simulta-Sy2tems Operating g Plant ID No.: HY-505 Th P Continuous P 1.a) Test Component: S lenoid Temperature Simulta-operated valves (op) Profile neous 112*F 10 A 1.b) Test Manufcctures Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Simulta-Model Number: Relative neous NP-0321A5E Humidity (%)

100 100 A 1.c) Test Punction:

Pilot valve Chemical ,

Simulta-Spray neous Accuricy: N/A B N/A 1.d) Test Servica: RCP Bleed Off Radiation Sequential Isoittion valve 2.12x106R 2 x 10 8R C,L 1.e) Test Ioc2 tion: 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 CDocumentation

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 lO2-B 11-1-80

.J )

Facility: . llctona Nuclev Pr. Sta.

Unit: Two ,

SYSTEM CCMPONENT EVALUATION WORK SHEET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTICN METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-Syr, tem : Waste Gas Operating neous Plant ID No.: HY-9126 Time P Continuous P 1.a) Test Component: Solenoid Temperature Simulta-operated valve ( F) Profile neous ll2*F 10 A 1.b) Test Manufteture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PS1C 10 A,H 1.b) Test Model Number: Relative Simulta-NP-8321ASE Humidity (%) neous Functirn: Pilot valve 100 100 A 1.c) Test

' Chemical Simulta-Spray neous Accurccy: N/A N/A B N/A 1.d) Test Servica: Waste gas tank Radiation Sequential I 8

inlet isolation valve 1.94x106R 2 x 10 R C,L 1.e) Test IocatiCn: Aux. Bldg. Aging Req. ma!nt.

El. (-) 5 ' 0" Sequential performsd Zone A-17 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abova Flood Levrl:s Yes Submergence nn CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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 103-B 11-1-80

Facility: tullstone 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.

imita-Sy; tem: S/G Blowdown Operating ne us Plant ID No.: HY-4246, Time 4248 P Continous P 1.a) Test Temperature Simulta-Component: Solenoid

( F) Profile neous opernted valves 112*F 10 A 1.b) Test Manuf:cture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIC 10 A,H 1.b) Test Simulta-Model Number: Relative neous NP-831655E Humidity (%)

Function: 100 100 A 1.c) Test Pilot valve ' Chemical Simulta-Spray neous Accurc_cy: N/A N/A B N/A 1.d) Test Servica: S/G blowdown Radiation Sequential 6 8 C,L 1.e) isoittion valve 1.94x10 R 2 x 10 R Test Icenticn: Aux. Bldg. Aging Req. maint.

El. (-) 5 ' 0" Sequential performed 40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-17 Flood Level Elev:

Abova Flood Level: Yes Subnergence No CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B c) 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 104-B 11-1-80

7 Facility- 1 ston2 Nuclear Pr. Stn.

Dockst: 50-336 DOCUtbhATION REF* QUAL. OUTSTANDING ENVIPO?DiENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spoc. Qual. Spec. Qual.

Simulta-Sy3 tem: Ctmt. Air Operatin9 neous Plant ID No.: HY-6080, Time P Continuous P 1.a) Test 6088 Simulta-Component: Solenoid Temperature

( F) Profile neous '

operrted valve Test 112*F 10 A 1.b)

ManufEcture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSlG 10 A,H 1.b) Test Simulta-Model Number Relative neous NP-831655 Humidity (g) 100 100 A 1.c) Test Function: Pilot valve

' Chemical Simulta-Spray neous securccy: N/A N/A B N/A 1.d) Test Se_vics: Ctmt. air recac Radiation Sequential coolsr control valve 1,94x106 R 2 x 108 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint.

El. (-) 5' 0" Sequential performed

'40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abovs Flood Level Yes Subnergence No CDocumentation

References:

Notes:

1. ASCO Test Report No. AQS 21678/TR Rev. B a) Appendix A Par. S b) Appendix A F1g. 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Par. 9.4.2.4.3 c) Appendix D lO6-B 11-1-80

x-FCcility: Cx,- illston3 Nuclr v Pr. Sta.

Unit: Two' SYSTEM COMPONENT EVALUATION WORK SHEET Dockst: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* OUTSTANDING QUAL.

METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Sptem: Ctat. Air Operating Simulta-Plant ID No.: HY-6072, Time neous 6075 P Continuous P 1.a) Test Component: Solenoid Temperature opernted valve Simulta-( F) Profile neous AS ll2*F 10 A 1.b) Test Manufteture: Pressure (PSIA) Simulta-profile neous 0.6 PSIG 10 A,H 1.b) Test Model Number: Relative Simulta-NP-831655 neous Humidity (%)

Function: Pilot % 1ve 100 100 A 1.c) Test

' Chemical Simulta-Spray neous Accur cy: N/A N/A B N/A 1.d) Test Servi,c'a : C % Air r; circ cooler inlet

, Radiation Sequential 1.16x106R 2 x 10 8R C,L 1.e) Test Aux. Bldg.

g tig: 5'0" Ai 9 Req. maint.

Sequential performed Zone A-17 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev Abova Flood Level: Yes Sulunergence nn CDocumentation

References:

Notes: This component must function in a

1. ASCO Test Report No. AQS 21678/TR Rev. B radiation (only) environment.

c) Appendix A Par. 5 b) Appendix A Fig, 9.2 c) Appendix A Par. 8.1.3 d) Appendix A Far. 9.4.2.4.3 e) Appendix D 107-B 11-1-80

)

u./

7-Q) ;

Facilit.y : lletone haclear Pr. Sta.

Unit Two SYSTEM COMPONENT ATION WORK SHEET Dockat: 50-336 ENVIRONMENT DOCUME!'TATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta-System: N2 Operating neous Plant ID No.: HY-7312 Time P Continuous P 1.a) Test Component: Pilot Temperature Simulta-solcnoid valve (oF) Profile neous ll2'F 10 A 1.b) Test Manuficture: Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 AH 1.b) Test Simulta-Model Number Relative neous NP-8320A189E Humidity (%) 100 A 1.c) Test 100 Funption:

Pilot valve Chemical Simulta-Spray neous Accurrcy:

g N/A B N/A 1.d) Test Servica: N2 stop valve Radiation Sequential to S.I .anks 1.94x106R 2 x 108 R C,L 1.e) Test Incntion: Aux. Bldg. Aging Req. maint.

El. (-) 5'0" Sequential performed Zone A-17 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Above Flood Level: Yes Subnergence nn .

CDocumentation

References:

Notes: This component must function in a

1. ASCO Test Report No. AQS 21678/TR Rev. B radiation (only) environment.

c) 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

(-

Fccility: 1, ton 2 Nuclear Pr. Sta.

SYSTEM COMPONENT ATION WORK SHEET Unit: Two Dockst: 50-336 EINIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Simulta- .

Sy tem: Reactor Coolant Operating neous Plant ID No.: HY 7690 Time P Continuous P 1.a) Test Simulta-Component: Solenoid Temperature operated valve ( F) Profile neous 112 F 10 A 1.b) Test Manuf cture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Simulta-Model Number Relative neous NP-8320A189E Humidity (%)

Function: Pilot valve 100 100 A 1.c) Test

' Chemical Simulta-Spray neous Accur cy: N/A N/A B N/A 1.d) Test Servic3: Radiation Sequential Reactor coolant sample 1.65x106R 2 x 108 R C,L 1.e) Test Incation: Aux. Bldg. Aging Req. maint.

El. (-) 5'0" Sequential performed Zona A-18 40 Years 4.4 Years PDL 1 Test every 3 yrs Flood Level Elev:

Abova Flood Level: Yes Suhnergence nn CDocumentation

References:

Notes: This component must function in a

1. ASCO Test Report No. AQS 21676/TR Rev. B radiation (only) environment.

c) 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 109-B 11-1-80

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Fncility: 11ctonn Nuclcnr Pr. Stn.

SYSTEM COMPONENT UATION WORK SHEET Unit: Two Dock;t: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS METHOD Parameter Spec. Qual. Spec. Qual.

Cntat. Sump Simulta-Sy; tem: Operating neous P13.at ID No.: HY-9150 Time P Continuous P 1.a) Test Component: Solenoid Temperature Simulta-( F) Profile neous operated valve 112*F 10 A 1.b) Test Manufceture: ASCO Pressure Simulta-(PSIA) Profile neous 0.6 PSIG 10 A,H 1.b) Test Simulta-Model Number: Relative neous NP-8321ASE Humidity (%)

100 100 A 1.c) Test Functicn: Pilot valve

' Chemical Simulta-Spray neous Accur cy: N/A N/A B , N/A 1.d) Test Servic3: Ctmt sump Radiation Sequential isolation valve 1.57x106R 2 x 108 R CL 1.e) Test Incatien: Aux. Bldg Aging Req. maint.

El. (-) 5'0" Sequential performed 40 Years 4.4 Years PDL 1 Test every 3 yrs Zone A-18 Flood Level Elev:

Abova Flood Level: Yes Subnergence na CDocumentation

References:

Notes: This component must function in a

1. ASCO Test Report No. AQS 21678/TR Rev. B radiation (only) environment.

e) 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 110-B 11-1-80

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Fccility: listons Nuclear Pr. Sta. ATION WORK SHEET SYSTEM COMPONENT Units Two Dockst: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING ENVIRONMENT EQUIPMENT DESCRIPTION MEM OD ITEMS Parameter Spec. Qual. Spec. Qual.

bee summary sht.

System: Cntat. Recirc Operating continuous 112B Plant ID No.: ZS-6080 Time ZS-6084 , ZS-6088, 6092 See sumary Component: Tdmit switch Temperature sheet 112B (OF) 35" ""--"LJ Manufreture NAMCO Pressure sheet ll2B (PSIA) 0.6 PSIG A,H See summary Model Ninnhar: SL3C Relative 100 A Function: Position ind. See sumary vnlva control ' chemical spray sheet ll2B N/A NA NA Accurccy:

dee sumary Cntmt. air Radiation sheet 112B Servics:

recirc cooler control 2.12x106R C,L d vs See summary Loc 2 tion: Agin9 Aux. Bldg. 40 Years- P.D.L. sheet 112B El. (-) 4 5 ' 6

Zona A18 Flood Level Elev:

Abov3 Flood Level: Yes Sulunergence un

• Documentation

References:

Notes: This compotent must function in a.

radiation (only) environment.

ll2-B 11-1-80

1128 graasARY 33EET 30.

128

.C:n N :T No.

lQ I

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EQUIPMENT ENTIBORGNTAL quaLIFICATI(Ni

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DISCRIPANT EQUIPMENT StBAGXY MILLSTONE 1NIIT 2 EQUIPMENT: STEM MOUNTED LIMIT SWITCHES ZS-6080, 6084, 6088, 6092 Containment Air itecirculation Cooler Control Valve MANUFACIURER: National Acme Corporation (NAMCO) l l

QUALIFICATI0W DISCREPANCT: These components lack documented qualification data.

SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

This equipment provide: contacts for control circuit input and position indication I for containment isolacion 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 position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that i procurement delays do not preclude replacement by that date. l I

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.o Facility: .

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Listona Nuclear Pr. Sta.

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3 SYSTEM COMPONENT ATION WORK SHEET Unit: Two Dockat: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING EINIRONMENT EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

See smnmnry System:

Primary Makeup Operating Continuous sheet ll3B Plant ID No.:

ZS-7311 Time Componnnt: Temperature See summary m swh gop) sheet 113B ll2 0 F A Pressure See smumary Manuficture: NM (PSIA) sheet 113B 0.6 PSIG A,H See summary Model Number: Relative Humidity (%) sheet ll3B 100 A Function: rosition ind. Chemical See simwnary

& valve control sheet ll3B Spray Accurccy: ^

N/A Quench tank Radiation See summary Servica: makeup sheet 113B watar entmt. isolation 1.94x106R C,L See summary INbN$n Aux. Bldg. Aging 40 Years P.D.L. sheet ll3B El. (-) S ' 0" Zone A18 Flood Level Elev:

Abova Flood Level: Yes Submergence nn CDocumentation

References:

Notes: This component must function in a radiation (only) environment.

ll3-B 11-1-80

l 113B SERetARY SEEET 30.

SCEW 5BEIT NO. Il3B U - Em.o m -CAT 1.

DISCREFANT EQUIPMENT StBefARY l

MILLSTONE IINIT 2 l EQUIPMENT: CfEM MOUNTED LIMIT SWITCHES 25-7311 i Quench Tank Makeup Water Conta nment Isolation Valve MANUFACTURER: National Acme Corporation (NAMCO)

B QUALIFICATION DISCREFANCT: 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 valve that 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 position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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&ccility: 11stons Nuclear Pr. Sta. hUATION WORK SHEET SYSTEM COMPONENT Unit: Two Docket: 50-336 DOCUMEIRATION REF* QUAL. OUTSTANDING ENVIRONMENT I EQUIPMENT DESCRIPTION METHOD ETEMS Parameter Spec. Qual. Spec. Qual.

See sumary 2 Operating Continuous sheet 116B jSy; tem:

Plcnt ID Ho.: ZS-7312 Time See surmmary Component: TAmi t switch Temperature sheet 116B 1120F A See summary Manufteture NAMCO Pressure sheet ll6B (PSIA)

O.6 PSIG A,H See summary

'Model Number: SL3C Relative 100 A Function: Position See summary Indication & valve ' Chemical sheet 116B control Spray N/A NA NA AccurIcy:

See sumary Servics: N2 stop valve to Radiation sheet 116B S.I. tanks 1.94x106R C,L m tion: Aux. Bldg. Aging See summary El. (-) 5'0" sheet 116B Zone A17 40 Years P.D.L.

Flood Level Elev:

Abov3 Flood Level: Yes Subnergence -

Hn

• Documentation

References:

Notes: This component must function in a radiation (only) environment.

116-B 11-1-80

A gematARY SEERT ED.

15h SCIW SEEET 30.

ov - 0 ,m -CA=N DISCEEFANT SQUIPNINT StBAGARY MILLS 1W E IINIT 2 1

I SQUIPMENTt STEM MOUNTED LIMIT SWITCHES ZS 7312 Nitorgen stop valve to safety injection tanks MANUFACTURER: National Acme Corporation (NAMCO) l QUALIFICATION DISCREFANCYt These components lack documented qualification data.

SAFETY FUNCTION AIB JUSTIFICATION FOR CONTINUED OFIEATICE:

, , This equipment provides contacts for control circuit input and position indication for containment isolation valves that function to mitigste a LOCA. They are all located outside the containment and are subject only to a radiation environment

i resulting from the LOCA. The control circuit operability requirement ceases within the first few seconds of the accident. Therefors, this equipment will ,

receive an insignificant radiation dose prior tc its required control operation.

Due to the desirability of long term position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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L Facility:

O-11 stone Nuclear Pr. Sta.

o ATION WORK SHEET Units Two SYSTEM COMPONENT Docket . 50-336 DOCUME N TION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ENVIRONMENT METHOD ITEMS Parameter Spec. Qual.. Spec. Qual.

See sinumary Primary Drain System: Operating Continuous t Plant ID No.: ZS-9016 Time Compontnt: Temperature See summary Limit switch (op) 112 F A sheet 119B "O S** ""'""#Y ManufIcture: Pressure (PSIA) sheet 119B O.6 PSIG A,H ,

3** ""#7 SL3C Relative sheet 119B Model Number:

00 A Function: Position l indication & valve " Chemical en saunan t control Spray sheet 119B N/A NA NA Accuracy:

• See summary Servica: Radiation sheet 119B' 7 Primary drain tank discharge isol 1.94x106R C,L i

Incation: Aging ee sn = ry Aux. Bldg. 40 Years P.D.L. sheet 1198

.El (-) 5,0 Zone A17 l Flood Level Elev:

Abova Flood Level: Yes Submergence no

• Documentation

References:

Notes: This component must function in a radiation l (only) environment.

119-B 11-1-80

graafAmT SEEET NO. Il9B SCIW EBERT NO. Il9B l C' ..

~

EQUIPMENT ENT m gantMTAL QUALIFICATI M A

DISCREFANT 5QUIPMENT StBAIARY MILLSTONE UNIT 2 EQU1FMENT: STEM MOUNTED LIMIT SWITCHES ZS-9016 Primary drain tank isolation valve MANUFACTUREE: National Acme Corporation (NAMCO)

QUALIFICATION DISCREFANCY: These components lack documented qualification data.

Oy SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

This equipment provides contacts for coerol circuit input and position indication for containment isolation valves that fun: tion to mitigate a LOCA. They are all lo.ated ou:: side 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 position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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((istonaNuclearPr.Sta.

Frcility:

SYSTEM COHPONENT ATION WORK SHEET Unit: Two' Dock 3t: 50-336 ENVIRONMENT DOCUME!TATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS Parameter Spec. Qual. Spec. Qual.

See summary Sy; tem: RCS Operating Continuous sheet 120B Plant ID No.: Time ZS-505 Compon:nt: Temperature See summary imit switch ( F) sheet 120B 112oF A Manufccture: Pressure See summary (PSIA) sheet 120B 0.6 PSIG A,H Model Number: Relative See simmary g

Humidity (s) sheet 120B 100 A Function: Position

' Chemical See summary indication & valve control Spray sheet 120B Accurrey:

N/A NA NA ee summary RCP Bleed ^ '" "

Service:

Off Isol. valv:

2.12x106R C,L Aux. Bldg. See summary Agi 9 ggtjo,9: 5'0" sheet 120B Zone A18 40 Years P.D.L.

Flood Level Elev:

Abova Flood Level: Yes Sulnergence NA NA NA NA NA NA no CDocumentation

References:

Notes: This component must function in a radiation (only) environment, j 120-B 11-1-80

[

)

l SE29fARY SEEET NO. 120B SCIW SREET NO. 120B

- - -Cm.

DISCRIPANT EQUIPMENT SIRetARY MILLSTONE IINIT 2 EQUIPMENT: STEM MOUltl'ED LIMIT SWITCHES ZS-505 Recctor Coolant pump bleed off 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 position indication operability of this equipment, it will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.

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Pacilitys k i ttne Nuclear Pr. Sta. ()

D SYSTEM COMPONENT JATION WC*tK SHEET l Urtit: Two l Docket: 50-336 DOCUMENTATION REF* QUAL. OUTSTANDING l EQUIPMENT DESCRIPTION ENVIRONMENT MEDIOD ITEMS Parameter Spec. Qual. Spec. Qual.

(

System Containment Press. Operating Sequential l Test Plant ID No.: Time Continuous Continuous 1,2,3

! PT-8238,8239 Temperature Simulta-Component: Pressure (OF) Profiles neous Transmitter ll2*F 28,31 A 1,3 Test Manufacture: Foxboro Pressure Simulta-(PSIA) Profiles neous Model Number: 0.6 PSIG 28,31 A,H 1,3 Test NEllCM-llCl-L-C-F Simulta-Relative Profiles neous Humidity (%) Test 100% 28,31 A. 1,3 .

Function: Wide range '

pressure indication 'dienical Simulta-Spray Profile neous

' 15 NA 1 Test Accur:cy: 0.5% span NA Radiation Sequential Service: Post 2.2 x 10 8 R accident monitoring 2.22x10 6R C 2 Test Aging See summar)

Io:ation: Aux. Bldg.

elev. (-) 5 '0" A17, A18 40 years P.D.L.

Flood IAnvel Eleva Sulzeergence NA NA NA Above Flood Level: Yes NA NA un fDoctamentation

References:

Notes:

1. Foxboro Test Report T3-1013

2. Foxboro Test Report T3-1068

3. Foxboro Test Report T3-6061 4

121-B 11-1-80

' 'SIDGERYtSEErr NO. 121B SCEW SHRET;,do. 121B I EQtrIPMEWFENTIEDWHENTAL QUALIFICATION

,DIse 3FANt BQUIPMERI'SID9tARY MIIIST0lW UNIT 2 Containment' Pressure Transmittere PT-8238, 8239 EQUIPMENT:

WANUFACTURER: Foxboro Model NEllGM-llCl-L-C-F QUALIFICATION +DISCREFANCY:.

.These components lack documented radiation and time / temperature aging qualification.

hh .SAFETO FUNCTION-AND JUSTIFICATION-FOR;CDHTINUED(OPERATION' This equipment. functions-to: provide vide range post accident indication of containment pressure.

An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Due to the present age of this equipment, the results of the aging analysis are not critical to establish reasonable assurance that the equipment will perform its function.

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ctone Nuclear Pr. Sta. f 9acility:

Unit- Two SYSTEM COMPOtGDrf Es ATION WORK SHEET W]

Doch24 50-336 ENVIROh W. DOCUMENTATION REF* QUAL. OUTSTANDING EQUIP)CNT DESCRIPTICE unwoo ITEnS Parameter W. Qual. Spec. Qual.

System Simulta-Systems Rad Monitoring Operating Design neous Plant ID No.: Z1RM8240/ Time Continuous Continuous (P. A.M. ) 1.a) Test B,C - Z2RM8241/B,C Simulta-Component: Coaxial cable Temperature neous (oy)

Profile 20 Profile 39 A,D 1.a) Test Pressure Simulta-Manufacture:

Rockbestos Co. (PSIA) neous Model Number: RSS 6-104 Note 1 Profile 39 A 1.a) Test Design' Simulta-

"9" *~ "" ""

Humidity (4) 1.a) Test 100% 100% ment. ,

Function: Rad monitoring cable ' M ical Spray Accuracy: Not required NA NA NA NA NA Service: low level signaly Radiation circuits' $! NA NA NA NA NA l'

Iocation: Various areas fi[ Aging Plant outside containment Design Sequential

- 40 Yrs. 40 Yrs. Life 1.c) Test Flood Imvel Elev:

Above Flood Level: Yes Submergence un

• Documentation

References:

Notes: 1. The pressure is 1.ess than 2PSIG for

1. Rockbestos report " Qualification of firewall III about 13 seconds. This is considered insignificant.

coaxial constructions dated January 18, 1978".

a) Page 2, Par. IV c) Page 2, Par. II 122-B 11-1-80

Pacility:

Unit O

b etone Nuclear Pr. Sta.

SYSTEM COMPCIEE3FF

()

J ATION WORK SHEET Docket: 50-336 ENVIROIEMENT DOCUBSNTATIOtt REF* QUAL. OtFFSTARIDING NQUIPDCNT DESCRIPTIOlt ITEns nETeOo l Parameter Spec. Qual. Spec. Qual.

Sy tem Reactor Cooling Operating Intermitt- 4195 Note 2. 2.a) Sequential Plant ID No. : RC403,RC405 Time ant Cycles Test Component: Valve Motor ature Simulta-Operat!ons F) Profile Profile neous 18 11 D 2.b) Test Isarmfacture s Pressure Simulta-Limitorque (PSIA) Profile Profile D 2.c) neous Model Number: Operator 19 llA Test S/N's 156210,156209,0rder No. 363562A nelative Simultd-Humidity (t) neous a Function: Pressure relief 100 100 1.-

2.d) Test -

icolation valve operators Chemical Simulta-Spray 2400 PPM neous

' Boron Note 1. F 2.e) Test Accuracy: Not required Service: Pory block valve Radiation Sequential 1.5 x 10 8

2.04x10 0R. K,L 2.f) Test Incation: Containment Aging 100 hrs at Plant EL 38f6" 180 C Design Sequential 40 Yrs. (40 Yrs.) Life 2.9) Test Flood Level Elev:(-)l4'4" Above Flood Imvel: Yes X Suhmargence NA NA NA NA NA un (Docuentation

References:

Notes: 1. Table 1, IEEE STD 382, Page 12

1. Bechtel Technical Spec. 7604-M-223A 2. Must operate int.ermittently during a TMI type 7604-E-40, 7604-E-llB evert 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 e) Par, 4.4.2 f) Par. 4.3.

g) Par 3.1.1 ,

1-C 11 1 80

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Facility: ctone Nuclear Pr. Sta.

U:it: Two - SYSTEM COMPOtG3rF JATI N WORK SHEET Do'chet: 50-336 I

ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING

( EQUIPMENT DESCRIPTICH METHOD IT1 DOS 1 _

Parameter Spec. Qual. Spec. Qual.

l l System Reactor Coolant ~ Operating Plant ID No.: Time l PT-103 i Components rature Simulta-Pressure Transmitter F) Profile Profile neous 18 318'F D , 1,34 Test Manufacture: Foxboro Pressure Simulta-

.(PSIA) Profile Profile neous Model Ntsaber: EllCM '

19 -90 PSI D 1,34 Test mladve Simulta-Mi=idi ty(4) Profile neous i

,. mtion: Lw range 100 100% 1,34 Test .

pre :urizer press. ' W "'l .

See sumary Spray 2400 PPM sheet 2C

' B ron F Accuracy: 1 0.5% -

Service: andiation See summary 8.2x106R K sheet 2C Incation: CntT (-) 5' ~NAG .

See sn-ary rack C-140 C-5 40 yrs, P.B.L sheet 2C

~

Flood Ievel Elev: 14'4" Above Flood Level: Yes X Submergence NA NA NA NA NA m l

' CDocumentation

References:

Notes: PT-103 S/N 2602027 i 1. Fcxboro Test Report Q-9-6005 2-C 11-1-80

TV ,

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+SCER SMIT No.

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UA DIsdRIPAlff' WltTIFMENY SUBSIARY 1t m g ly 2 ^

EQUIPMENT Low Range Pressurizer Pressure Transmitters PT-103

J Foxboro E-11GM MANUFACTURER:

QUALIFICATION DISCREPANCYt This equipment lacks documented qualification data concerning resistance to chemical spruy and radiation exposure.

O -

SAFETY FUNCTION AND JUSTIFICATION Q FOR CottTINUED OPERATIONt PT-103 provides_ signal _ input,for tae post accident monitoring,_a_ubcooling margin monitor. This component serves as post accident low range l 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.

The overpressure protection for the shutdown cooling system is provided for in the plant operating procedw ea and ensured through administrative controls. Wide range monitors are e44,o available to provide operating

!1 personnel with pressurizer pressure indication for shutdown cooling system initiationo re Due to the desirability of'loeg term position indication operability of this equipment, it will be' replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June.30, 1982, assuming that procurement delays.do rat preclude replacement by that date.

An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

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, Facility ctone Nuclear Pr. Sta.

Untit: Two SYSTEM COMPONDrr JATION WORK SlutET Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION ITEMS i

NEDIOD i_ Parameter Spec. Qual. Spec. Qual.

See summary Cy; tem: RCS Operating continuous sheet SC l

Plant ID No. : TEll2HA-D, Time l TEl.^2HA-D,TEll2CA-D, ITE122CA-D component: Connection ature Profile 16, See summary HEd F) 18 D 1 sheet SC Manufacture Rosemount Pressure Profile 16.

(PSIA) 19 D 1 See summary Model Numbers (TEll2HC- sheet SC 104ADA 104AFC-1) '

anlative 100% D See suemary manidity(g) 1 sheet SC Function: RCS, loop temp.  ;

RTD Cable Termination 'dismical 2400 ppm Spray boron F 1 See summary Accuracy: 8 sheet SC Service: Radiation 1.5 X'ld I See summary K 1 sheet SC Incation: CTHI C-5 Aging See summary 40 yrs. P.D.L. sheet SC m

Flood Level Elev: (-)l4 '4 N/A N/A N/A N/A N/A Above Flood Level: Yes i Submergence un (Documentation

References:

Notes:

1. 8-27-79 letter from J. Graham, Rosemount Engineering to R. K. McCarthy 5-C 11-1-80

l SC StBetARY SIEET 30.

SC SCDI $8EET NO.

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EQUIPMENT ENTIE01BENTAL QUALIFICATION DISCRIPANT FNIFMEllI SUBMARY msTOIR UNIT 2 EQUIPMENT:

RCS loop temperature RTD connectidn heads TE-ll2CA-CD TE-ll2HA-HD TE-122CA-CD TE-122HA-HD MANUFACTURER: Rosemount QUALIFICATION DISCREPANCY:

These components lack documented qualification data.

SAFETY FUNCIION AND JUSTIFICATION FOR CONTINUED OPERATION:

These components provide protection for the cable terminations of the referenced RTD's. These RTD's provide control room indication of the monitored parameters and RPS input for the thermal margin / low pressure trip setpoint determinations.

Reasonable assurance that these components will provide the required protection is provided by Reference 1 on system component evaluation work sheet.

Due to the desirability of long term position indication operability of this equipment, it will be replaced with' qualified equipment. This will be accomplished as soon as practicable, prior'to June 30, 1982, assuming that procurement delays dc not preclude replacement by that date.

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l Facility l Units Two\

stone Nuclear Pr. Sta. (Q SYSTEM COMPOtGNT E( JATION WORK SHEET l Docket: 50-336 l

EINIRONMENT DOCUMEttrATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION 1112tS l.

METHOD EE Sil 454 Parameter Spec. Qual. Spec. Qual.

l I Systems Aux. Feed Water Operating Sequential l

Plant ID No. : Fr-5277, Time Continuous Continuous 1,2,3 Test 5278 Temperature Simulta-Component: Differential (OF) Profile Profile neous pressure transmitter 326*F 28,31 20A 1,3 Test Manufacture: Foxboro Pressure Simulta-(PSIA) Profile neous Model Numkr NE13D11 1.8 PSIG 28,31 A 1,, 3 Test Relative Simultd-Humidity (t) Profile neous 100 28,31 A 1,3 Test .

. Function: Aux. feed -

flow indication 'th-ical Simulta-Spray Profile neous

' NA 1 Test Accuracy: =0.5% NA 15 Services Radiation Sequential 2.2 x 10 8 R 2 Test Iocation: 2..ne A-51 Aging See summary 40 yrs. P.D.L. sheet 8C m

m Flood Level Elev:

Above Flood Levels Yr? Salmnergence un CDomumentation

References:

Notes:

1. Foxboro Test Report T3-1013

2. Foxboro Test Report T3-1068

3. Foxboro Test Report T3-6061 e

8-C 11-1-80

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,.a -m StatfARE SEEIT NO.

8C o., . .

80 ,

s. SCEW SHEET NO. 1

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N W TIB019tWTAL QUAI,IFICATION

, ~ 's MILIsTONE UNIT 2 BQUIPfGNT: , Differential pressure transmitters for auxiliary feedwater flow indication FT-5277, 5278 MANUFACIURER: Foxboro Model NE-13DH

' QUALIFICATION DI.0CREPANCY: These components lack documented radiation and time / temperature aging qualification.

O g SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:

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 the present age of.this equipment, the results of the aging analysis are not critical to establish. reasonable assurance that the equipment will perform its function.

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A Pacilitys 'jctor=NuclearPr.Sta. (

SYSTEM COMPONENT E( . ON WORK SHEET 6

Unit: Two.

Docket: 50-336 ENVIPONMENT DOCUMENTATION REF* QUAL. OUPSTANDING EQUIPMENT DESCRIPTION EEQ Sli 450 452 Parameter Spec. Qual. Spec. Qual.

Systen: Main Steam Operating Sequential Plant ID No. : LT-1113B,C,D Time Contim.ous Continuous 4 1,2,3 Test LT-ll23B,C,D Component: Differential Temperature Simulta-pressure transmitter ( F) Profile Profile neous 16 28,31 D 1,3 Test Manufacture: Foxboro Pressure Simulta-(PSIA) Profile Profile neous Model Number: 19 28,31 D 1,3 Test NE-13-DM-HI-M2 Relative Simultd-Humidity (%) Profile neous Function: Steam genera- 100 28,31 .

1,3 Test -

tor level " Chemical Simulta-Spray 2400 PPM Profile neous

' 1 Test Accuracy: 0.5% span Boron 15 F Service: Radiation Sequential 6

8.2 x 10 R 2.2 x 108 R K 2 Test Incation: CTMT 14'6" C-5 Aging See summary 40 yrs. P.D.L. sheet 9C s

Flood level Elev(-)l4 '4" Above Flood Level: Yes X Submergence NA NA NA NA NA un CDocusentation

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 e

9-C 11-1-80

1 SIRMART SEEET NO. 9C SCEV SHEET NO. 9C g

EQUIPMDIT ENVIE010 ENTAL QUALIFICATION DISCREFANT EQUIPMENT SUIMART 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.

O SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OFERATION:

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.

-An independent laboratory has been contracted by NUSCO to provide radiation and time / temperature aging analysis for this equipment.

Due to the present age of this equipment, the results of the aging analysis are not critical to establish reasonable assurance that the equipment will perform its function.

0

/

O U tone Nuclear Pr. Sta. hATION WORK SHEET (/'3 Pccility:

Unit: Two SYSTEM COMPONENT (V

Docket: 50-336 DOCUNDFTATION REF* QUAL. OUTSTANDING JER.TIPMENT DESCRIPTION ENVIROtMENT MEDIOD ITEMS EE SH 486 Qual.

Parameter Spec. Qual. Spec.

System RPS Operating continuous continuous 1, 2 Simultaneou:

Plant ID No.: Time Test PS-4597 A,B,C,D Component: Pressure Temperature 155 F Simtaltaneous

( F) 160"F Profile 1, 2 Test switch 22 Manufacture: Custom Pressure Simultaneous Compoinnt (PSIA) 0.5 PSIG 16.0 PSIA Profile 1, 2 Test Model Number: 22 CCS 604GR6-356S Balative 100% 100% Profile Simulta'neous Ibmaldity(%) 22 1, 2 Test

• Function: Turbine trip _

' Chemical l

Spray jAccuracy:

8 N/A Service: Radiation N/A See summary Ioc; tion: Zone Til Aging 40 Years P.D.L. sheet 14C Flood Level Elev: N/A N/A N/A N/A N/A N/A Above Flood Level: Yes Suhnergence un CDocumentation

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 e

14-C 11-1-80

i t.S +(ry!@;;;., - ' t >

.  ;' ._z.  ;;

. ' ' " [ ,,.

r* -  ; 4 ,.

14C

^

g g. g 14C '

O 4 V ,

'I y . ,.,W,gygggggyEAL QUA1.IFICAT10N l

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DIS (RWitrm3QUIPttENT.StR9dARY '

, '"MILLSTW BcVNIT.2 Pressure Switches PS-4597A, B, C, D EQUI 7tNKF:

-High pressure turbine ' hydraulic fluid pressure ygggy g , Custem Component Switches (CCS)

These components lack documented time /

QUALIFICATION DISCRIPANCY:

temperature aging qualification data.

' SAFETY FUN 6 TION AND JUSTIFICATION POR/CONTINUEDiOFERATION:

These components function to cause a reactor trip on loss of turbine hydraulic fluid pressure.

An independent: laboratory has been contracted by NUSCO to provide time / temperature aging analysis for this equipment.

Due to the present age of this equipment, the results of the aging analysis are not critical.to establish reasonable assurance that the equipment will perform its function.

l 1

i I

l Oi ,

w 1 l

Facility '

Unit:

stone Nuclear Pr. Sta.

SYSTEM COMPONENT El

( ON WORK SHEET

/Q

,U Docket: 50-336 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING HETHOD ITEMS Parameter Spec. Qual. Spec. Qual.

Cyrten: Radiation Monit. Operating Simulta-Plant ID No.: Time neous RE 8240, 8241 Continuous Continuous 1 Test a Component: High range Temperature Simulta-

!,rcdiation detector (OF) Profile neous 18 340'F D Test a Manufacture: Pressure Simulta-

General Atomic (PSIA) Profile neous Model Number

RD-23 19 70 PSIG D Test a Relative Simulta-Humidity (%) neous

, Function: Accident / post 100% 100% D Test a .

' Onemical cccident radiation Simulta-monitoring spray 2400 PPM 3000 PPM neous

, Accuracy: + 3%

• Boron Boron F Test a Service: Radiation Sequential 1.5 x 10 8R' l.0 x 10 9 R K Test a Incation: CTMT Aging elev. 16'6" Sequential

, 40 Yrs. 40 Yrs. PDL Test a Flood Level Elev:(-)l4'4" Abova Flood Level: Yes X Sulmergence NA NA NA NA NA NA un '

CDocumentation

References:

Notes _: a. This equipment is purchased on a risk release

1. Millstone II FSAR Table 7.5.2 basis pending completion of the vendor test report and our subsequert review & acceptance. The vendor has tested this equipmen; to the requirements and parameters identified in IEEE STD 323-1974 appendix A. The applicable qualifi-cation documentation references will be identified when received.

Vendor has estimated the test report completion date to be December 1980.

15-C 11-1-80

jo 'n Facility j c(e__. stone Nucl=r Pr. Sta. ,, .)

..,JATION WORK SHEET j

Units Two ' SYSTEM COMPONENT I

Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEnIOD ITEMS Parameter Spec. Qual. Spec. Qual.

'*" #~

Sy; tem Post Accid. Monit. Operating -

Plant ID Ho.: LT-8242, Time Continuous Continuous 1 Te a 8243 Component: Level Trans- Temperature Simulta-mitter (Oy) Profile neous 18 381'F D Test a Manufactures GEM Pressure Simulta-(PSIA) Profile neous Model Number: 19 60 PSIG D Test a XM-548532-84-1500 Simulta-Relative os dity N D a 100% 100% Test

• Function: Containment ~

sump level indication " Chemical Simulta-Spray 2400 PPM neous Accuracy: 8 Boron ph=ll.0 F Test a Service: Post accident Radiation Sequential monitoring 1.5 x 10 8 R 2.0 x 10 8R K Test a Iocation: CTMT AC 2 4 Sequential elev.(-)22'6"-(-)15'6" 40 Yrs. 40 Yrs. PDL Test a Flood Ievel Elev:(-)l4 '4" Above Flood Level: Yes Submergence a Hn Y CDocumentation

References:

Notes: a. This equipment is purchased on a risk release basis pending completion of vendor qualification testing and NUSCO review and acceptance of the fi: ' . test reports.

The target date .'or rec'eipt of the vendor's, final test report is 10-81. The qualification documentation

. . references will be identified at that time.

~

16-C 11-1-80

Fccility:f laton2 Nuclear Pr. Sta.

Unit Twc, SYSTEM COMPONENT E4..uUATION WORK SHEET Dock 2t: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEU!OD ITEMS Parameter Spec. Qual. Spec. Qual. _

PZR relief valve Simulta-Syrtens monitors Operating s Plant ID No. : ZS200,201, Time Continuous Continuous 1 Test a 402,404 Component: Accelerometer Tsuperature Simulta-(OF) Profile neous 16,18 Profile 41 D 1 Test a Manufrcture: Endevco Pressure Simulta-(PSIA) Profile neous Modal Number: 2273AM20 16,19 Profile 42 D 1 Test a Simulta-Relative Humidity (t) neous 100% 100% D 1 Test a .

Function: Post accident '

monitoring ' Chemical Simulta-Spray 2400 PPM 3000 PPM neous Accur cy: 8 Boron Boron F 1 Test a Service : Porv . discharge Radiation Sequential line monitoring 1.5 x 108 R 2 x 108 R K 1 Test a Location: CTMT C-5 Aging Plant To Be Design Sequential

. 40 yrs. Determined Life 1 Test a,b Flood Imvel Eiev:(-)14'4" Above Flood Imvel: Yes X Submergence un CDoctamentation

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.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ r __ 9 _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

f-Facilitys f ;t:n3 Nuclear Pr. Sta, (g)

U SYSTEM COMPCHENT ION WORK SHEET Units Two Docket: 50-336 ENVIRONMENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT CESCRIPTION ITEMS ME'n!OD Parameter Spec. Qual. Spec. Qual.

PZR relief valve Simulta-Systeen monitors operating neous Plant ID No.: ZS-200,201, Time 1 Test a Continuous Continuous 402,404 ,

Component: Cable Temperature Simulta-FF) Profile neous 16,18 Profile 41 D 1 Test a Manufacture: Harline Pressure Simulta-Cc.ble Endevco (PSIA) Profile neous Model Number: 3075M6 16,19 Profile 42 D 1 Test a Simulta-aelative neous Humidity (%)

100% 100% D. 1 Test a .

- Function: Post accident ~

monitoring ' Onessical Simulta-Spray 2400 PPM 3000 PPM neous

' Boron F 1 Test a Accuracy: Boron service: Porv discharge andlation Sequential line monitoring 1.5 x 108 R 2 x 10 8R K 1 Test a Incation: CTMT C-5 Aging Plant To Be Design Sequential

- 40 yrs. Determined Life 1 Test a,b Flood Level Elev:(-)14'4" Abovo Plood Level: Yes X Submergence un CDoctamentation

References:

Notessa. This equipment is purchased on a risk release

1. Babcock & Wilcox, valve monitoring system, basis pending coupletion 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 determined in accordance with IEEE 323-1974 guidelines.

18-C 11-1-80

/N Facilitys h C itone Nuclear Pr. Sta.

Unit: Two- SYSTEM COMPOtENT E\

f TION NORK SHEET

(

Docket: 50-336 ENVIRONMENT DOCUMDITATION REF* QUAL. OUTSTANDING EQUIPMENT CESCRIPTION METHOD ITEMS Pariumeter Spec. Qual. Spec. Qual.

PZR relief valve Simulta-Systess a monitors Operating neous Plant ID No.: ZS-200,201 Time 402,404 Continuous Continuous 1 Test a Component: Preamplifier trature Simulta-y) Profile neous 16,18 Profile 41 D 1 Test a Manufacture : "nholtz- Pressure Simulta-Dickie (PSIA) Profile neous Model Number: 22CA-ZTR 16,19 Profile 42 D 1 Test a Simulta-Relative Rtamidity (4) "" "8 100% 100% D 1 Test a .

Function: Post accident '

monitoring " Cheunical Simulta-Spray 2400 PPM 3000 PPM neous

' a Accuracy: Boron Boron F 1 Test service: Porv diacharge Radiation Sequential line monitoring 1.5 x 108 R 2 x 108 R K 1 Test a Incation: CTKf C-5 Aging Plant To Be Design Sequential

- 40 yra. Determined Life 1 Test a,b r-Flood Level Elev (-)14'4" 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 and test program 3-21-80. NUSCO review and acceptance of the fina' test reports. The target date for receipti 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.

_ _ _ _ _ _ _ - . - _ . _ - _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ AC%ro _ __Jul_J -f76L __ _ _ __ _ __ ___ _ _ __ _ __ _ __ _ _ _ __ __ _

Facility:

Unit: Two' tone Nuclear Pr. Sta.

GYSTEM COMPONENT ni,UATION WORK SHEET

('

Docket 50-336 ENVIROk4(ENT DOCUMENTATION REF* QUAL. OUTSTANDING EQUIPMENT DESCRIPTION MEntOD ITEMS Parameter Spec. Qual. Spec. Qual.

PZR relief valve Simulta-Sy", tem s monitors pg;;,g g P1:nt ID lio. : ZS-200,201 Time Continuous Continuous 1 Test a 402,404 Component: Junction Box ature Simulta-y) Profile neous 16,18 Profile 41 D 1 Test a Manufacture: Hoffman Pressure Simulta-(PSIA) Profile neous Model Number: 8064 CHNESS 16,19 Profile 42 D 1 Test a Simulba-Relative neous Humidity (%) a est ,

Function: Post accident ~

monitoring " Chemical Simulta-Spray 2400 PPM 3000 PPM neous

~ Accuracy: ' Boron Boron F 1 Test a Service: Pory discharge Andiation Sequential line monitoring 1.5 x 108 R 2 x 108 R K 1 Test a Incation: CnfT C-5 Aging Plant To Be Design Sequential

- 40 yrs. Determined Life 1 Test a,b Flood Level Elev:(-)l4'4" Above Flood Level: Yes X Sulmergence un

• Doctamentation

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 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 determined in accordance with IEEE 323-1974 guidelines.

1 i

7 \

l l

1 DOCUMENT REFERENCE LIST SUPPLEMENT O A. - Bechte1 Nuclear Staff Calcu1stion 532-27-11867 Rev. 0: Computer Run x3022, 11/3/79.

B. The Chemical solution consists of 3000 PPM Boron as Boric Acid in so1ution with'0.064 Molar sodium Thiosulfate buffered with Sodium Hydroxide to a PH of between 9 and 10 at Room Temperature, f C. NUSCO response 'to NUREG-0578-Section 2.1.6b, Attachment 2, Sununary Sheets, W. G. Counsil to H. R. Denton, December 31, 1979.

D. NUSCO memorandum C.. J. Gladding to R. J. DeRosa CME-80-274 dated February 29,-1980.

E. NUSCO memorandum C. J. G1 adding to R. J. DeRosa GME-80-701 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.

O 1. NuSCO me orandum C. J. 01addin8 to R. J. DeRosa GME-80-863 dated July 7, 1980.

J.

K. NUSCO memorandtsa 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, 1980.

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.

L  !

l l

I MISCELLANEOUS ELECTRICAL DEVICES b

A list of miscellaneous 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 tne containment as shown on SCEW sheet 13A. Environmental conditions b 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, considered insignificant especially since the connectors.are housed in metal enclosures and would likely never reach the == m nt temperature.

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 installed in metal enclosures and it is.unlikely that their environment would ever reach destructive levels. The temperature transient is relatively short lived and diminishes to less than 2000 F in two minutes. Also, the conclusion reached in the reference a) observation and stated judgement is that the 3-M Skotch-Lok connector, when compared with the Ideal Sec Screw connector is A a better device for mechanical integrity and lower circuit leakage.

U b

MiccellcnerusElGetricalDevich;s Pcg2 2 O Terminal Blocks - GE EB-5 and other types (unidentified) b

' '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 onen that successfully withstood LOCA. simulation tests while energized with 525 volts AC..

1 Due to the desirability of long term operability of this equipment, they I

will be replaced with qualified equipment. This will be accomplished as soon a.s practicable, prior to. June.30, 1982, assuming that procurement delays do not preclude replacement,by that date.

Butt Splices These devices have been identified as being installed only inside the conteinment in one valve circuit. No specific qualification has been obtained thus far, however,. 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 desir' ability .of .long . term operability of this equipment, it Q

will be replaced with qualified ' equipment. This will be accomplished as soon as practicable, prior to June 30,.1982, assuming that procurement delays do not preclude replacement by that date.

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,

110 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, coatinued plant operation is justified.

Dae to_the desirability of long term operability of this equipment, it-i will be replaced with qualified equipment, relocated or further protected.

' This will be accomplished as soon as practicable prior to June 30, 1982 s.ssuming that procurement delays do not preclude replacement by that date.

Reference a) NUSCO memorandum, J. M. Clark to R. J. DeRosa GRE-80-233 '

dated October 14,'1980.

i 1 .'

[ 11/1/80-r 1 ..

rO ,

O O

~2 k 346*F/li3 psig within S MIN LEGEND

- INSUL ATION RESISTANCE 346 - MEASUREMENT gg 335 -  ! # 9 2.-@

o, 315 - h h

\ \ 315*F/69psig "E

P2 8% ..

aav e @ '

E' E y  : 265'F/28psh 5.2 3265- "

am N w

S lS g3 b $

280*F/70psig within 10 SEC

• 212 F/O-5psig IR O R O

' 212 -

w.

=

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ONCE PER WEEK I

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{ gp gR HR HR HR HR DAYS 45 MIN DAYS

% {

e EL APSED TIME  ;

co co CO P

, FIGURE 1. Specified temperature, pressure, and radiation test profile -  !

FIRL Test. Report F-C4020-1 This profile has been designated by the vendor as

" Confidential'?. Therefore, it has not been

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's'bmitted with this package. It is available at Northeast Utilities for Audit,'however.

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l PROFILE 3

!, 11/1/80 i-

_ LOCA Profile -f  !

Spray continuously at rate of 0.15 gpm

. .lt 346*F/li3 psig ( min) per square foot of spray area with 30 -

I_

/ WITHIN 3TO 5 MIN

( 2 solution of the following composition:

0.28 molar H 3B03 (3000 ppm boron)

NaOH to make pH between 9-11 at 77,F.

335'F/93 psig 320 -

e 315'F/69 psig s

- *---265' F/28 psig 9

$ E 3 250 --  %

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mone e [ untve (O l A= P20 Dean 1= . sc cr 4: ua rtco n uA10NITsR/N6 .S. . t 7rsr psggy,, 32,.9o .

                                                                                                                            -i Pressure in Containment vs. Time                                                                           .

Envelope bf Owners 100 PSI 10 SEC 100 - i 11 HOURS 80 - f e 7 e 8 HOURS 60 PSI 7 (J 60 -

                                                           ~

h 15 HOURS 4 OAYS 40 - 25 PSI

     .20   -

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     .0                                                                                   10,000            100,000 100                    1,000 100             10                     .

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1 TAst.E 18

SUMMARY

OF TESTS WITH HEAT EXCHANGER A) Exposure Times: Motor Running Hours Time in high pressure etsam (above 76 psig) 24 Total posteocident time (18 peig) 168 Time of chemical sprey . 24 Motor starts in steem High pressure 9 , (full lood) Low pressure 5 Number of rapid pressurlastions 7

                .             5) Post Exposure Tests
                  .                                                          Befse sesem                      After Steam Ex -                               Ex -

1) Overpotential test Not required Passed. IR shown (1200 volte rms. 80 Hz below taken imm-for 1 minute) ediately afterwords i

2) Inedstion reeletence low speed = 80 mogohme hi$ epeed a 150 mogohms

3) Vihretion (men in.) @.0017 e.0017

4) Steft loessness, vertios: 0.006 in. 0.006 in.

5) Cossadoom tiene iminutes) leerspeed 8% 8%

hi$ speed 12 12

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I TsSTs unwouT wAT,;axcumesan .e r. v .- A wmmary of dote tek&n during the Ave high+ressure transiente (21 hours above 75 ps.gl followed by esven days et 14 peig is g% in Table 17. l Figure 18 shows how the motor enciesure pressure built up during the steem inrush. The pressure differsnoe across the bearings was essentially zero thereefter. Atsention in celled to Jw fact that esturation of steem temperatures were reached during each of the h8p-pressure cycles. h TA8tE 17

                '                                  $UMe4ARY OF OS8dRVATIONS-TESTS WITHOUT HEAT EXCHANGER

q. . ..

l' A) Exposure Times: Reeter Running l Time in hi$ pressure steem (above 75 psig) 21 hours Total poeteccident time (16 peig) 7 days Time of chemical sprey 20 imrs Motor starts in stoom High pressure 9 starts Low pressure 5 starts (full lood)

                           -                     Number of rapid pressuriaations                                                5 si inspeeden
                      -                                                             Before Steem                       After Steam Exposure                          Exposure

1) Owpotential test Not required Passed I (1200 volte rms, 60 Ha for 1 minuta)

2) Insutetion resistence low speed winding 1000 megohms 700 mogohms l i high speed winding 1000 mogohms 700 mogohms i si sheft looseness 0.000in. 0.006 in. .

di Ossetdown time (minutes) low speed 84 8X high speed 12 12 y

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TABLE 4 O .t ORIGINAL AND IRRADIATED - STEAM EXPOSED ELECTRICAL TEST DATA HYFALON JACKETED CABLES Capacitance Power Insulation Resistance Picofarads Factor Megohms /ft per Foot (1000 Hz) 7. 11 x 106 51 1.6 Original 7 Irradiated Cables - 5 x 10 RADS after Steam Exposure

• First Cycle Infinity 51.7 1.23 Room temperature 13,636 58.4 11.34 47 psi steam 5,910 55.8 7.80 27 pai steam Third Cycle 2,180 57.3 9.10 48 psi steam 2,090 55.7 7.40 28 psi steam- ,

Fifth Cycle _ ,,s [ I

                            /I                                        57.3       8.87 790 50 psi steam 1,000             56.0      7.39    l 30 psi steam 90,190              53.1       1.61 Room temperature

• Steam-Exposure: 5 cycles of 20 minutes at 45 psi and 30 minutes.at 30 psi per cycle gfphooucCP FAMC#Rf REPer g f N E M t. C A R Li*

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,i . - .- l i DOCKET NO. 50-336 i [O i' i 1 NORTHEASI NUCLEAR ENERGY COMPANY 1 } MILLSTONE UNIT NO. 2 i i APPENDIX III i 1 I RESPONSE TO AUDIT REPORT i

                                                                      . DATED OCTOBER 14, 1980 J

t i t ! I i I. tO L J, t )1 i l l l i I I

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                                                       .                                                                                                                          OCTOBER, 1980 e

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In Reference (28), the NRC Staff provided Northeast Nuclear Energy Company (~)x

  \_   (NNECO) with a report of the findings of an inspection conducted at Millstone Unit No. 2 to verify component installation as identified and reported in response to I&E Bulletin No. 79-01B. Within the scope of the inspection conducted on September 23 - 26, 1980, no items of non-compliance were observed and the inspector verified that the components identified by NNECO in response to I&E Bulletin No. 79-OlB were installed at Millstone Unit No. 2.

The inspector identified three (3) discrepancies between the reported system / component identification and the actual installation as reported in Reference (1). NNECO provides the following information in response to these items. Item 1 Electrical motors (2) used to actuate Fuel Handling Damper Nos. HV-8275 and HV-8326 were not identified on Pages 198 and 199, respectively, of Appendix I. These dampers are not required to mitigate the consequences of a steam line break outside containment and, therefore, are not required to be included in the response to I&E Bulletin No. 79-OlB. The damper identified on Page 198 of Appendix I as HV-8274 is a typographical error. The correct damper number is HV-8275. The error is corrected in Appendix I to this report. Item 2 () Although flow switch FS-8141 is an integral part of flow recorder, FR-8412, the two components act as separate electrical circuits and as such, are treated as separate components. The flow switch provides a dry contact output for the flow recorder. Flow switch, FS-8141, is listed as Foxboro Part No. 50 and included on Page 196 of Appendix I. Flow recorder, FR-8412, is listed as Foxboro Part No. 70 sud included on Page 12 of Appendix I. Item 3 Conduit carrying safety-related electrical cables were identified with a non- i safety-related designation. The conduit identified in Reference (28) carries safety-related cabling from solenoid valve HY-8141 and is supported seismically. NNECO will re-label this conduit with a designation identifying it as safety-related by January 1, 1981. I O

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