ML13323A158
| ML13323A158 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/07/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Dietch R, Gilman D SAN DIEGO GAS & ELECTRIC CO., SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 8107140002 | |
| Download: ML13323A158 (42) | |
Text
JUL
'JUL 71981Ui UCE Docket Nos.:
50-361/362 Mr. Robert Dietch Mr. D. W. Gilman Vice President Vice President - Power Supply Southern California Edison Company San Diego Gas'& Electric Company 2244 Walnut Grove Avenue 101 Ash Street P. 0. Box 800 P. 0. Box 1831 Rosemead, California 91770 San Diego, California 92112 Gentlemen:
SUBJECT:
STATUS OF SAN ONOFRE 2 AND 3 OPEN ITEMS In Supplement No. 2 to the San Onofre 2 and 3 SER we identified seven items that had not yet been resolved. This letter documents our understanding of the current status of these items, an additional item that was discussed in our letter of April 16, 1981, and another new item described in Enclosure 5 to this letter. Enclosure 1 lists the remaining open items, the status of each, and, for those items where additional submittals are necessary, the dates that have been established by your staffffor the additional submittals. We request that you make every effort to meet these dates, so as to avoid impacting the San Onofre Unit 2 schedule.
Also, we request that you provide us with a list of the present status and schedule for submittal of the "Confirmatory Items" discussed in Section 1.8 of the SER and its supplements.
If you have any questions regarding the items discussed herein, please contact the staff project manager.
Sincerely, Original signed by Robert L. Tedesco Robert L. Telesco, Assistant Director for Licensing Division of Licensing DISTRIBUTION:
Enclosures:
Docket File 50-361/362
- 1. Open Items as of 7/1/81 LPDR FJMiraglia
- 2.
EQB Evaluation Report
- 4. Request for Add. Info. -
Reactor TERA K (3)
Vessel Level Instrumentation LB#3 Files ACRS (16)
- 5.
Second & Later Cycle Power Distributions DEisenhut C
See ne page.RPurple OFFICE DLEtB DL:
L SURNAMEO--
-alY_
RLT esco 8107140002 810707 DATE PDR ADOCK 05000361 81 PDDHoo NRC FORM 318 (10/80) NRCM 0240',
OFIILRCR OY-
- USGPO:
1980-329-824 OFFICIALNSI JEOReeOP
Mr. Robert Dietch Mr. D. W. Gilman cc:
Charles R. Kocher, Esq.
James A. Beoletto, Esq.
Southern California Edison Company 2244 Walnut Grove Avenue P. 0. Box 800 Rosemead, California 91770 Chickering & Gregory ATTN:
David R. Pigott, Esq.
Counsel for San Diego Gas & Electric Company Southern California Edison Company 3 Embarcadero Center - 23rd Floor San Francisco, California 94112 Mr. George Caravaiho City Manager City of San Clemente 100 Avenido Presidio San Clemente, California 92672 Alan R. Watts, Esq.
Rourke & Woodruff Suite 1020 1055 North Main Street Santa Ana, California 92701 Lawrence Q.
Garcia, Esq.
California Public Utilities Commission 5066 State Building San Francisco, California 94102 Mr. V. C. Hall Combustion Engineering, Incorporated T000 Prospect Hill Road Windsor, Connecticut 06095
Mr. Robert Dietch
- 3 Mr. D. W. Gilman cc:
California Department of Health ATTN: Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1111 Howe Avenue Sacramento, California 95825
- Chairman, Board of Supervisors San Diego County San Diego, California 92412 Mayor, City of San Clemente San Clemente, California 92672 U. S. Environmental Protection Agency ATTN: EIS Coordinator Region IX Office 215 Freemont Street San Francisco, California 94111 Energy Resources Conservation &
Development Commission ATTN:
Librarian 111 Howe Avenue Sacramento, California 95825.
ENCLOSURE 1 STATUS OF SAN ONOFRE 2 AND 3 OPEN ITEMS AS OF JULY 1, 1981 ITEM STATUS (1) Environmental Qualification Staff audit conducted May 11-15, 1981.
of Equipment No major deficiencies noted. Summary of staff findings given in Enclosure 2.
Applicant to provide revised submittal by September 1, 1981.
(2) Core Protection Calculator Final applicant submittal to be provided by July 30, 1981.
(3) DNBR Testing of Revised FEA Staff review of CEN-165-(-S)-P in progress.,
Conclusion to date is that DNBR of 1.19 is acceptable for standard CE 16 x 16 fuel element. The effect of non standard San Onofre 2 and 3 grids and grid spacing still under review by the staff.
(4) Emergency Planning Revised site Emergency Plan submitted June 1, 1981.
Letter addressing FEMA deficiencies submitted June 26, 1981.
Submittal of additional revisions to site EP scheduled for July 6, 1981.
(5) Seismic Scram Submittal of conceptual design and implementation schedule due July 13, 1981.
(6) Financial Qualifications Outstanding information to be submitted by August 1, 1981.
(7) Inadequate Core Cooling See Enclosures 3 and 4, Response to Instrumentation is requested by September 1, 1981.
(8) Instrumentation and Control Staff letter describing concerns issued Systems Items April 16, 1981. Applicant submittal due July 20, 1981.
(9) Second and Later Cycle Power See Enclosure 5.
Distributions
ENCLOSURE 2 EQUIPMENT EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE UNITS 2 and 3 DOCKET NO. 50-361, 362 3 STAFF EQUIPMENT EVALUATION The staff evaluation of the applicant's response includes an onsite inspection of selected Class IE equipment, audits of qualification documentation, and an examination of the applicant's report for completeness and acceptability. The criteria described in NUREG-0588 form the basis for the staff evaluation of the adequacy of the applicant's qualification program.
The NRC Office of Inspection and Enforcement (IE) will perform, in the near future, an onsite verification inspection of selected safety-related electrical equipment. The inspection will verify proper installation of equipment, overall interface integrity, and manufacturer's nameplate data. The manufacturer's name and model number from the nameplate data will be compared to information given in the Component 'Evaluation Work Sheets (CES) of the applicant's.submittal.
The staff performed an audit of the applicant's environmental qualification program on May 11-15, 1981. The audit included detailed reviews of supporting documentation for eight equipment items. No major deficiencies were noted.
However, the applicant should provide a revised submittal before fuel load.
The revision should include results of the aging review and analysis to extend qualification from 30 to 120 days after an accident. The revision should reflect all modifications and additions to which the applicant committed during the audit.
The results of the audit are summarized in an audit report dated June 1, 1981.
3.1 Completeness of Safety-Related Equipment In accordance with NUREG-0588, the applicant was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA and an HELB and (2) identify components needed to perform the function of safety-related display information, post-accident sampling and monitoring, and radiation monitoring.
The staff developed a generic master list based upon a review of plant safety analyses and emergency procedures. The instrumentation selected includes parameters to monitor overall plant performance as well as to monitor the per formance of the systems on the list. The systems list was established on the basis of the functions that must be performed for accident mitigation (without regard to location of equipment relative to hostile environments).
The list of safety-related systems provided by the applicant was reviewed against the staff-developed master list.
Based upon information in the applicant's submittal, the staff has verified and determined that the systems included in the applicant's submittal are those required to achieve or support: (1) emergency reactor shutdown, (2)
containm'ent isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of significant release of radioactive material to the environment. The staff therefore concludes that the systems identified by the applicant (listed in Appendix D) are acceptable.
Display instrumentation which provides information for the reactor operators to aid them in the safe handling of the plant was identified by the applicant.
A complete list of all safety-related display instrumentation was provided.
Justification for discrepancies between the staff's master list and the appli cants list was provided. The discrepancies are the result of differences in design.
The applicant identified 103 items types of equipment which were assessed by the staff.
3.2 Service Conditions Commission Memorandum and Order CLI-80-21 requires that the "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safety-related electrical equipment environmental qualification program. This document provides the option of establishing a bounding pressure and temperature condition based on plant-specific analysis identified in the applicant's Final Safety Analysis Report (FSAR) or based on generic profiles using the methods identified in these documents.
On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes for San Onofre Units 2 and 3 relative to the temperature, pressure, and the containment spray caustics, has been performed in accordance with the requirements stated above. The staff has reviewed the qualification documentation to ensure that the qualification specifications envelope the conditions established by the applicant.
Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result from HELBs.
3.3 Temperature, Pressure, and Humidity Conditions Inside Containment The applicant has provided the results of accident analyses as follows:
Max Temp (oF)
Max Press (psig)
Humidity (%)
LOCA 287 55.1 100 MSLB 405.6 54.2 100 The applicant's specified temperature profile for qualification purposes envelopes only the LOCA temperature profiles. The applicant has provided an analysis to show that the equipment surface and/or equipment internal temperature during the MSLB does not exceed the qualification temperature.
The staff can not accept the qualification based on the internal temperature unless a detailed failure mode of the various components of the equipment (including gaskets and seals) is provided. Hence, for those components which were qualified based on the internal temperature, the applicant should either provide the detailed failure mode of the various components of the equipment or should requalify the equipment based on the higher MSLB temperature.
3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The applicant has provided the temperature, pressure, humidity, and applicable environment associated with an HELB outside containment. The following areas outside containment have been addressed:
(1) Main steam and feedwater line valve rooms (2)
Auxiliary feedwater pump room (3) Charging pump room The staff has verified that the parameters identified by the applicant for the HEL8 are acceptable.
3.5 Submergence The maximum submergence levels have been established and assessed by the applicant. Unless otherwise noted, the staff assumed for this review that the methodology employed by the applicant is in accordance with the appropriate criteria as established by Commission Memorandum and Order CLI-80-21.
The applicant's value for maximum submergence is 25 ft. Equipment below this level has been identified by the applicant, along with the proposed corrective action. The applicant identified four types of safety-related electrical components as having the potential for becoming submerged after a postulated event.
The containment emergency outlet valve operators and the containment temperature sensor have been relocated above flood level. An analysis is being performed to exempt from qualification the excore detectors and preamplifiers.
Justifica tion was provided for the valve operators and containment sump level transmitters.
These items perform their functions before submergence, and their subsequent failure will not degrade the safety of the plant or mislead an operator.
3.6 Chemical Spray The applicant's FSAR value for the chemical concentration is 1720-2300 ppm boron and NaOH injection, resulting in a pH greater than 9. The exact percent used by the vendor for qualification testing should be verified by the applicant.
Therefore, for the purpose of this review, the effects of chemical spray will be considered unresolved. The staff will review the applicant's response when it is submitted and discuss the resolution in a supplemental report.
3.7 Aging NUREG-0588 Category II delineates two aging-program requirements. Valve operators committed to IEEE Standard 382-1972 and motors committed toIEEE Standard 334-1971 must meet the Category I requirements of the NUREG. This requires the establishment of a qualified life, with maintenance and replacement schedules based on the findings. All other equipment must be subjected to an aging program which identifies aging-susceptible materials within the component.
Additionally, the staff requires that the applicant:
(1) Establish an ongoing program to review surveillance and maintenance records to identify potential age-related degradations.
(2) Establish component maintenance and replacement schedules which include considerations of aging characteristics of the installed components.
The applicant identified a number of equipment items for which a specified qualified life was established (for examples, 5 years, 15.years, or 40 years).
In its assessment of these submittals, the staff did not review the adequacy of the methodology nor the basis used to arrive at these values; the staff has assumed that the established values are based on state-of-the-art technology and are acceptable.
For this review, however, the staff requires that the applicant submit supple mental information to verify and identify the degree of conformance to the above requirements. The response should include all.the equipment identified as required to maintain functional operability in harsh environments.
The applicant indicated that this phase of the response is outstanding and that the review is in progress. The staff will review the applicant's response when it is submitted and discuss its evaluation in a supplemental report.
3.8 Radiation (Inside and Outside Containment)
The applicant has provided values for the radiation levels postulated to exist following a LOCA. The application and methodology employed to determine these values were presented to the applicant as part of the NRC staff criteria con tained in NUREG-0588 and in the'guidance provided in IEB-79-01B, Supplement 2.
Therefore, for this review, the staff has assumed that, unless otherwise noted, the values provided have been determined in accordance with the prescribed criteria. The staff review determined that the values to which equipment was qualified enveloped the requirements identified by the applicant.
The value required by the applicant inside containment is an integrated dose of 2 x 108 rads, which envelopes the minimum requirements of NUREG-0588.
A required value of 1 x 106 rads has been used by the applicant to specify limiting radiation levels for RHR equipment within the the auxiliary building.
This'value considers the radiation levels influenced by the source term methodology associated with post-LOCA recirculation fluid lines and is acceptable.
4 QUALIFICATION OF EQUIPMENT The following subsections present the staff's assessment, based on the applicant's submittal, of the qualification status of safety-related electrical equipment.
The staff has separated the safety-related equipment into three categories:
(1) equipment requiring immediate corrective action, (2) equipment requiring additional qualification information and/or corrective action, and (3) equip ment considered acceptable if the staff's concern identified in Section 3.7 is satisfactorily resolved.
In its assessment of the applicant's submittal, the NRC staff did not review the methodology employed to determine the values established by the applicant However, in reviewing the data sheets, the staff made a determination as to the stated conditions presented by the applicant. Additionally, the staff has not completed its review of supporting documentation referenced by the applicant (for example, test reports). It is expected that when the review of test reports is complete, the environmental qualification data bank established by the staff will provide the means to cross reference each supporting document to the referencing applicant If supporting documents are found to be unacceptable, the applicant will be required to take additional corrective actions to either establish qualifi cation or replace the item(s) of concern.
An appendix for each subsection of this report provides a list of equipment for which additional information and/or corrective action is required.
Where appropriate, a reference is provided in the appendices to identify deficiencies.
It should be noted, as in the Commission Memorandum and Order, that the deficien cies identified do not necessarily mean that equipment is unqualified. However, they are cause for concern and may require further case-by-case evaluation.
4.1 Equipment Requiring Immediate Corrective Action Appendix A identifies equipment (if any) in this category. The applicant was asked to review the facility's safety-related electrical equipment. The applicant's review of this equipment has not identified any equipment requiring immediate corrective action; therefore, no deficiency reports were submitted.
In addition, in this review, the staff has not identified any safety-related electrical equipment which is not able to perform its intended safety function during the time in which it must operate.
4.2 Equipment Requiring Additional Information and/or Corrective Action Appendix B identifies equipment in this category, including a tabulation of deficiencies. The deficiencies are noted by a letter relating to the legend (identified below), indicating that the information provided is not sufficient for the qualification parameter or condition.
Legend R
radiation T
- temperature QT -
qualification time RT required time P
pressure H
humidity CS - chemical spray A
- material-aging evaluation; replacement schedule; ongoing equipment surveillance S
submergence M - margin I - HELB evaluation outside containment not completed QM -
qualification method RPN - equipment relocation or.replacement; adequate schedule not provided EXN - exempted equipment justification inadequate SEN - separate-effects qualification justification inadequate QI - qualification information being developed RPS - equipment relocation or replacement schedule provided As noted in Section 4, these deficiencies do not necessarily mean that the equipment is unqualified. However, the deficiencies are cause for concern and require further case-by-case evaluation. The staff has determined that an acceptable basis to exempt equipment from qualification, in whole or part, can be established provided the following can be established and verified by the applicant:
(1) Equipment does not perform essential safety functions in the harsh environ ment, and equipment failure in the harsh environment will not impact safety-related functions or mislead an operator.
(2a) Equipment performs its function before its exposure to the harsh environ ment, and the adequacy for the time margin provided is adequately justified, and (2b) Subsequent failure of the equipment as a result of the harsh environment does not degrade other safety functions or mislead the operator.
(3) The safety-related function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single-failure criterion.
(4) Equipment will not be subjected to a harsh environment as a result of the postulated accident.
The applicant is, therefore, required to supplement the information presented for equipment in this category before full acceptance of this equipment can be established. The staff will review the applicant's response, when it is sub mitted, and discuss the resolution in a supplemental report.
4.3 Equipment Considered Acceptable or Conditionally Acceptable Based on the staff review of the applicant's submittal, the staff identified the equipment in Appendix C as (1) acceptable on the basis that the qualifi cation program adequately enveloped the specific environmental plant parameters, or (2) conditionally acceptable subject to the satisfactory resolution of the staff concern identified in Section 3.7.
For the equipment identified as conditionally acceptable, the staff determined that the applicant did not clearly (1) state that an equipment material evaluation was conducted to ensure that no known materials susceptible to degradation because of aging have been used, (2) establish a program to review the plant surveillance and maintenance records in order to identify equipment degradation which may be age related, and/or (3) propose a maintenance program and replacement schedule for equipment identified in item I or equipment that is qualified for less than the life of the plant.
The applicant is, therefore, required to supplement the information presented for equipment in this category before full acceptance of this equipment can be established. The staff will review the applicant's response.when it is sub mitted and discuss the resolution in a supplemental report.
7
APPENDIX A Equipment Requiring Immediate Corrective Action (Category 4.1)
Item Equipment Manufacturer Model Deficiency None in this category.
A-1
APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
Designation for Deficiency R -
Radiation T - Temperature QT - Qualification Time RT -
Required Time P - Pressure H -
Humidity CS -
Chemical spray A - Material aging evaluation, replacement schedule, ongoing equipment surveillance S -
Submergence M -
Margin I - HELB evaluation outside containment not completed QM - Qualification method RPN - Equipment relocation or replacement, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualification justification inadequate QI - Qualification information being developed RPS - Equipment relocation or replacement schedule provided Equipment Manufacturer/
Description Model #
Component No.
Deficienc Circuit Breaker Panel Comsip-Delphi AC3BLPO3 QT,A,QI Boards Circuit Breaker Panel Comsip-Delphi BC4BLPO4 QT,A,QI Boards Circuit Breaker Panel Comsip-Delphi AC3BLP1O QT,A,QI Boards Circuit Breaker Panel Comsip-Delphi BC4BLP11 QT,A,QI Boards (A)Electrical Penetrations Westinghouse low voltage, QT,A power and control Electrical Penetrations Westinghouse low voltage, QT,A large conductor Electrical Penetrations Westinghouse coax and triax QT,A (A) Audited item B-1
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency (A)Electrical Penetrations Westinghouse medium voltage QT,A 600V Control &
Raychem (Flamtrol)
M(R),QT,A Instrumentation Cable 600V Control &
Rockbestos M(R),QT, Instrumentation Cable (Firewall III)
A,QI 600V Control &
Rockbestos M(R), QT, Instrumentation Cable (Firewall III)
A,QI 600V Power Cables GE(Vulkene)
QT,A Special Purpose Cable Bendix T,P,HR,A, QI Cable and Wire Connector Amp. Inc. (PVF)
M(PR),
QT,A Heat Shrinkage Connection Raychem (MCK)
QT,A Kits Heat Shrinkable Sleeves Raychem (WCSF-N)
M(R),QT, A
Environmental Seal Conax QT,A Assemblies Motor Reliance (447T)
AB5BE399 QT,A Motor Reliance (447T)
AB5BE400 QT,A Motor Reliance (447T)
AB5BE401 QT,A Motor Reliance (447T)
AB5BE402 QT,A Fan Motor Reliance (444T)
AB6BAO71 QTA Fan Motor Reliance (444T)
AB6BAO72 QT,A Fan Motor Reliance (444T)
AB6BAO73 QT,A Fan Motor Reliance (444T)
AB6BAO74 QT,A Fan Motor Reliance (444T)
AB6BAO75 QT,A (A) Audited Item B-2
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Pump Motor Siemens-Allis (AZ) AJlP141 T,P,H,R,A, QI Pump Motor Siemens-Allis (AZ) BJ1AP504 T,P,HR,A, QI Pump Motor Westinghouse AN1APO24 QT,A (5810L)
Pump Motor Westinghouse WN1APO25 QT,A (5810L)
Pump Motor Westinghouse BNIAPO26 QT,A (5810L)
Motor Reliance (182T)
BN1BE445 A,QT Motor Reliance (182T)
AN1BE517 A,QT Motor Reliance (182T)
BN1BE455 QT,A Motor Reliance (182T)
BN1BE518 QT,A Motor Reliance (182T)
AN1BE454 QT,A Motor Reliance (182T)
ANIBE453 QT,A Motor Reliance (184T)
ANIBE416 QT,A Motor Reliance (182T)
BPIBE435 QT,A Motor Reliance (182T)
BPIBE436 QT,A Motor Reliance (182T)
APIBE437 QT,A Motor Reliance (182T)
APIBE438 QT,A Motor Reliance (213T)
ANIBE417 QT,A Motor Reliance (213T)
AJIBA394 M(P),QT,A Motor Reliance (213T)
BJIBA443 M(P),QT,A PRV Position Indication TP,HR,A, System QI Radiation Monitor General Atomics T,PH,R,A, Instrumentation QI B-3
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency H2 Recombiner Westinghouse AB5BE145 M(R),QT,A H2 Recombiner Westinghouse BB5BE146 M(R),QT,A H2 Recombiner Power Westinghouse AC3RL180 T,PH,R,A, Supply Panel QI H2 Recombiner Power Westinghouse BC4RL181 T,P,H,R,A, Supply Panel QI Pressure Transmitter Foxboro PT0353-1 TP,H,R,A, QI Pressure Transmitter Foxboro PT0354-2 T,P,HR,A, QI Level Transmitter GEMS (XM-36498)
LT9386-1 T,PR,H,M, QT,A,QI Level Transmitter GEMS (XM-36498)
LT9389-2 T,PR,H,M, QT,A,QI Level Transmitter GEMS (XM-36498)
LT9387-2 T,P,R,H,M, QT,A,QI Level Transmitter GEMS (XM-36498)
LT9388-1 T,PR,H,M, QT,A,QI Level Transmitter GEMS (XM-36498)
LT5853-1 T,P,RH,M, QT,A,QI Level Transmitter GEMS (XM-36498)
LT5853-2 T,P,R,HM, QT,A,QI Limit Switch Magnetrol LSH9450-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9451-1 SQTA (FLS-X-MPX)
Limit Switch Magnetrol LSH9452-1 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9453-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9454-2 S,QT,A (FLS-X-MPX)
B-4
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Limit Switch Magnetrol-LSH9455-2 Q,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9456-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9457-1 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9458-1 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9459-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9460-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9462-1 SQT,A (FLS-X-MPX)
Limit Switch" Magnetrol LSH9463-2 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9464-2 SQT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9465-1 S,QT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9466-1 SQT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9467-2 SQT,A (FLS-X-MPX)
Limit Switch Magnetrol LSH9471-1 S,QT,A (FLS-X-MPX)
Solvenoid Valve ASCO HY9823 M(R),QTA (NP831664E)
Solvenoid Valve.
ASCO HY9824 M(R),QT,A (NP831664E)
Solenoid Valve ASCO HY9204 T,P,H,RA, (HTX8320Al85V)
RPS 8-5
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Solenoid Valve ASCO HY8419B T,P,H,RA, (HT8316D45)
-RPS Solenoid Valve ASCO HY8419C T,P,H,R,A, (HT8316D45)
RPS Solenoid Valve ASCO HY8421B T,P,H,R,A, (HT8316D45)
RPS Solenoid Valve ASCO HY8421C T,P,H,R,A, (HT8316D45)
RPS Solenoid Valve ASCO (NP Series)
HY0509 QT,A Solenoid Valve ASCO (NP Series)
HY0511 QT,A Solenoid Valve ASCO (NP Series)
HY0513 QT,A Solenoid Valve ASCO (NP Series)
HY5804 QT,A Solenoid Valve ASCO (NP Series)
HY7513 QT,A Solenoid Valve ASCO (NP Series)
HY7911 QT,A Solenoid Valve ASCO (NP Series)
HY7259 QT,A Solenoid Valve ASCO (NP Series)
HY9920 QT,A Solenoid Valve ASCO (NP Series)
HY9921 QT,A Solenoid Valve ASCO (NP Series)
HY9948 QT,A Solenoid Valve ASCO (NP Series)
HY9951 QT,A Solenoid Valve ASCO (NP Series)
HY9821 QT,A Solenoid Valve ASGO (NP Series)
HY9825 QT,A Solenoid Valve ASCO (NP Series)
HY9218 QT,A Solenoid Valve ASCO (NP Series)
HY6212 QT,A Solenoid Valve ASCO (NP Series)
HY6213 QT,A B-6
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Solenoid Valve ASCO (NP Series)
HY6218 QT,A Solenoid Valve ASCO (NP Series)
HY6219 QT,A Solenoid Valve ASCO (NP Series)
HY6500 QT,A Solenoid Valve ASCO (NP Series)
HY6501 QT,A Solenoid Valve ASCO HY9200 T,P,HR,A, (HTX8320A108V)
ASCO HY9205 T,P,H,RA, (HTX8320A105V)
RPS Limit Switch NAMCO (EA-.180)
ZSH9204-2 QT,A Limit Switch NAMCO (EA-180)
ZSL9204-2 QT,A Limit Switch NAMCO (EA-180)
ZSH9823-1 QT,A Limit Switch NAMCO (EA-180)
ZSL9823-1 QT,A Limit Switch NAMCO (EA-180)
ZSH9824-2 QT,A Limit Switch NAMCO (EA-180)
ZSL9824-2 QT,A Limit Switch NAMCO (EA-180)
ZSH9971-2 QT,A Limit Switch NAMCO (EA-180)
ZSL9871-2 QT,A Limit Switch NAMCO (EA-180)
ZSH9340-2 QTOA Limit Switch NAMCO (EA-180)
ZSL9340-2 QT,A Limit Switch NAMCO (EA-180)
ZSH9350-1 QT,A Limit Switch NAMCO (EA-180)
ZSL9350-1 QT,A Limit Switch NAMCO (EA-180)
ZSH9360-1 QT,A Limit Switch NAMCO (EA-180)
ZSL9360-1 QT,A Limit Switch NAMCO (EA-180)
ZSH9370-2 QT,A Limit Switch NAMCO (EA-180)
ZSL9370-2 QT,A B-7
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #'
Component No.
Deficiency Limit Switch NAMCO (EA-180)
ZSH & ZSL0509-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL0511-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL0513-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL0515-2 QTA Limit Switch NAMCO (EA-180)
ZSH & ZSL5388-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL5437-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL5804-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL7513-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL7911-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL7259-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9918-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9920-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9921-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9945-1 QTA Limit Switch NAMCO (EA-180)
ZSH & ZSL9948-2 QTA Limit Switch NAMCO (EA-180)
ZSH & ZSL9951-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9821-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9825-1 QT,A Limit Switch NAMCP (EA-180)
ZSH &-ZSL9218-1 QT,A Limit Switch NAMCO (EA-180)
ZSH &.ZSL5434-2 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL9200-1 QTA Limit Switch NAMCO (EA-180)
ZSH & ZSL9205-1 QT,A Limit Switch NAMCO (EA-180)
ZSH & ZSL6212-2 QT,A 8-8
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficiency Limit Switch NAMCO (EA-180)
ZSL6212A1 QT,A Limit Switch NAMCO (EA-180)
ZSL6212B1 QT,A Limit Switch NAMCO (EA-180)
ZSH6213-2 QT,A Limit Switch NAMCO (EA-180)
ZSL6213-2 QT,A Limit Switch NAMCO (EA-180)
ZSL6213A2 QT,A Limit Switch NAMCO (EA-180)
ZSL621382 QT,A Limit Switch NAMCO (EA-180)
ZSH6218-1 QT,A Limit Switch NAMCO (EA-180)
ZSL6218-1 QT,A Limit Switch NAMCO (EA-180)
ZSL6218A1 QT,A Limit Switch NAMCO (EA-180)
ZSL6216B1 QT,A Limit Switch NAMCO (EA-180)
ZSL6219-2 QT,A Limit Switch NAMCO (EA-180)
ZSL6219A2 QT,A Limit Switch NAMCO (EA-180)
ZSL6219A2 QT,A Limit Switch NAMCO (EA-180)
ZSH6500-2 QT,A Limit Switch NAMCO (EA-180)
ZSL6500-2 QT,A Limit Switch NAMCO (EA-180)
ZSH6501-1 QT,A Limit Switch NAMCO (EA-180)
ZSL6501-1 QT,A Motor-Operated Valves Limitorque HV9900 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limftorque HV9971 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9917 M(T,R),QT, (SMB,SB)
A.
Motor-Operated Valves Limitorque HV9946 M(T,R),QT, (SMB,SB)
A B-9
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficiency Motor-Operated Valves.
Limitorque HV5803 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV7258 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV6223 M(T,R),QT, (SMB,SB)
A.
Motor-Operated Valves Limitorque HV6236 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV7512 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9304 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9305 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9334 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9340 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9350 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9360 M(T,R),QTj (SMB,SB)
A Motor-Operated Valves Limitorque HV9370 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9201 M(TR),QT, (SMW,SB)
A Motor-Operated Valves Limitorque HV9267 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9337 M(T,R),QT, (SMB,SB)
A B-10
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Motor-Operated Valves Limitorque HV9339 M(T,R),QT, (SMBSB)
A Motor-Operated Valves Limitorque HV9377 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9378 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV0508 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV0510 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV0512 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV0514 M(T,R),QT, (SMB,SB)
A Motor-Operatd Valves Limitorque HV0516 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV0517 M(T,R),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV9217 M(TR),QT, (SMB,SB)
A Motor-Operated Valves Limitorque HV5686 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV6366 QT,A (SMB,SB)
Motor-Operated Valves Limistorque HV6367 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV6368 QT,A (SMBSB)
Motor-Operated Valves Limitorque HV6369 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV6370 c QT,A (SMBSB)
B-11
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Motor-Operated Valves Limitorque HV6371 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV6372 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV6373 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9336 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9359 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9379 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9306 QTA (SMB,SB)
Motor-Operated Valves Limitorque HV9307 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9347 QT,A (SMB,SB)
Motor-Operated Valves Limitorque HV9348 QT,A (SMB,SB)
Solenoid Valve Valcor HV0352(A-D)
QT,A (V52600-539)
Solenoid Valve Target Rock (75G)
HVO501 QT,A Solenoid Valve Target Rock (75G)
HV0503 QT,A
- Solenoid, Valve Target Rock (75G)
HV7803 QT,A Solenoid Valve Target Rock (75G)
HV7810 QT,A Solenoid Valve Target Rock (75G)
HV7811 QT,A Solenoid Valve Target Rock (75G)
HV7816 QT,A B-12
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Motor-Operated Valve Limitorque (SMB)
HV6211 QT,A Motor-Operated Valve Limitorque (SMB)
HV6216 QT,A Motor-Operated Valve Limitorque (SMB)
HV9353 QT,A Motor-Operated Valve Limitorque (SMB)
HV9302 QT,A Motor-Operated Valve Limitorque (SMB)
HV9303 QT,A Motor-Operated Valve Limitorque HV8150 QT,A (SMB-1-40)
Motor-Operated Valve Limitorque HV8151 QT,A (SMB-1-40)
Motor-Operated Valve Limitorque HV8152 QT,A (SMB-1-40)
Motor-Operated Valve Limitorque HV8153 QT,A (SMB-1-40)
Motor-Operated Valve Limitorque HV9949 QTA (SMB-1-40)
Motor-Operated Valve Limitorque HV9950 QTA (SMB-1-40)
Limit Switch Limitorque HV8150 T,PH,R,A, Assembly (SMB-0-40)
RPS Limit Switch Limitorque HV8151 T,P,H,R,A, Assembly (SMB-0-40)
RPS Limit Switch Limitorque HV8152 T,PH,RA, Assembly (SMB-0-40)
RPS Limit Switch Limitorque HV8153 T,PH,R,A, Assembly (SMB-0-40)
RPS Limit Switch Limitorque HV9949 TP,H,R,A, Assembly (SMB-0-40)
RPS Limit Switch Limitorque HV9950 TPH,R,A, Assembly (SMB-0-40)
RPS Main Steam Marrotta HV8204.
H,A Isolation Valve (MV238C)
-h*
B-13
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficiency Relay Potter-Brumfield HV8205 H,A,RPS (MDR-5060)
Cable GE (Vulkene)
H,A (A)Thermocouple Weed TE9903-1,
M(T,P),QT, (1000-512-0021)
A Thermocouple Weed TE9911-2 M(T,P),QT,.
(1000-512-0021)
A Hydrogen Sensor GE (47E240610)
AET8100-1 PCS,QT,QI, A
Hydrogen Sensor GE (47E240610)
AET8101-2 PCS,QTQI, A
Pressure Transducer CEC (CEC 1000)
PT8112-2 H,CSQTQI, A
Pressure Transducer CEC (CEC 1000)
PT8111-1 HCSQT,QI, (A) RTD Rosemount TE9178 (1-4)
M(TR),QT, (104-AFC-1)
A (A) RTD Rosemount TE0112 (1-4)
M(T,R),QT, (104-AFC-1)
A (A) RTD Rosemount TE9179 (1-4)
M(T,R),QT, (104-AFC-1)
A (A) RTD Rosemount TE0122 (1-4)
M(T,R),QT, (104-AFC-1)
A (A) RTD Rosemount TE0111X1 M(TR),QT, (104-AFV-1)
A (A) RTD Rosemount TE0111Y1 M(TR),QT, (104-AFV-1)
A (A) RTD Rosemount TEO911X1 M(T,R),QT, (104-AFV-1)
A (A).RTD Rosemount TEO911Y1 M(T,R),QT, (104-AFV-1)
A (A) Audited item B-14
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency (A) RTD Rosemount TE0921X2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0121X2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0121Y2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0921Y2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0915-2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0115-2 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0925-1 M(T,R),QT, (104-AFV-1)
A (A) RTD Rosemount TE0125-1
{(T,R),QT, (104-AFV-1)
A RCP Speed Signal Bentley-Nevada SE-0113 (1-4)
T,P,HR,A, (21956)
QI Sensor and Transmitter Bentley-Nevada SE-123 (1-4)
T,PH,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada SE-133 (1-4)
TP,H,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada SE-143 (1-4)
TP,H,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada ST-113 (1-4)
- T,P,H,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada ST-123 (1-4)
TP,H,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada ST-133 (1-4)
TP,H,R,A, (21956)
QI Sensor and Transmitter Bentley-Nevada ST-143 (1-4)
T,PH,R,A, (21956)
QI (A) Audited item B-15
APPENDIX 8 (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Pressure Transmitter Foxboro (E-11 GM)
PTO101 (1-4)
T,P,MA,QI Pressure Transmitter Rosemount PT102 (1-4)
TP,M,QT, (1153-GA9)
A,QI Pressure Transmitter Rosemount PT0102-1,*2 TP,M,QT, (1153-GA9)
AQI Differential Pressure Foxboro (E-13 DH)
LT-110 1, 2 T,P,M,QT, Transmitter A,QI Pressure Transmitter Foxboro (E-11 GM)
PT0103-1 TP,M,AQI Pressure Transmitter Foxboro (E-11 GM)
PT0105-3 T,PM,A,QI Pressure Transmitter Rosemount PT-0104-2 T,P,M,AQI (1153-GA9)
Pressure Transmitter Rosemount PT-0106-4 TPM,AQI (1153-GA9)
Pressure Transmitter Foxboro (E-11 GM)
PT 1013 (1-4) fP,MA,QT, QI Pressure Transmitter Foxboro (E-11 GM)
PT 1023 (1-4)
T,P,MA,QT, QI Pressure Transmitter Foxboro (E-11 GM)
PT 1013 1, 2 TP,MA,QT, QI Pressure Transmitter Foxboro (E-11 GM)
PT 1023 1, 2 T,PM,A,QT, QI Differential Pressure Foxboro (E-13 DM)
LT-1113 (1-4)
T,P,M,A,QI Transmitter Differential Pressure Foxboro (E-13 DM)
LT-1123 (1-4)
TP,M,AQI Transmitter Differential Pressure Rosemount LT1115 1, 2 TP,M,A,QI Transmitter (1153 DA5)
Differential Pressure Rosemount LT1125 1, 2 T,PMA,QI Transmitter (1153 DA5)
Nuclear Instrument General Atomics/
None TA,R,H,CS,QI Detector Assembly Reuter Stokes (EIE 304-5000-1)
B-16
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficiency Position Transmitter CE & Electro None P,R,HA,CS, Mechanics QI..
Nuclear Instrument General Atomics/
None T,P,H,R,CS, Preamplifier/Filter Reuter Stokes QI$ A Excore Detector.System ITT None T,P,QM,R, Cable QI,QT,A RSPT Cable Anaconda None T,P,R,QM, QT,QI,A RTD Rosemount TE0303-1, 2 QT,A (104-AFC-1)
RTD Rosemount -
TE0351-1 QT,A (104-AFC-1)
RTD Rosemount TE0352-2 QTA (104-AFC-1)
Pressure Sensors Foxboro (E-11 GM)
PT0303-1, 2 QT,A,QI Pressure Sensors Foxboro (E-11 GM)
PT-0351 (1-4)
AQI Pressure Sensors Foxboro (E-11 GM)
PT-0352 (1-4)
A,QI Flow Sensor Foxboro (E13 DA)
FTO311-2 QT,AQI Flow Sensor Foxboro (E13 DA)
FT0321-1 QTAQI Flow Sensor Foxboro (E13 DA)
FT0331-1 QTAQI Flow Sensor Foxboro (E13 DA)
FT0341-2 QT,A,QI Flow Sensor Foxboro (E13 DA)
FT9421-1 QT,A,QI Flow Sensor Foxtloro (E13 DA)
FT9435-2 QTA,QI Flow Sensor Foxboro (E13 DM)
FT0338-1 QTA,QI Flow Sensor Foxboro (E13 DM)
FT0348-2 QTAQI Flow Transmitter Foxboro (E-96)
FT0318 T,P,RH,A, RPS Flow Transmitter Foxboro (E-96)
FT0328 T,P,R,H,A, RPS B-17
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficiency Flow Detector Foxboro (2801)
FE-0318 TP,H,R,A, RPS Flow Detector Foxboro (2801)
FE-0328 TP,H,R,A, RPS Level Transmitter Foxboro (E13-DMP)
LT-0348-1 T,P,H,R,A, RPS Level Transmitter Foxboro (E13-DMP)
LT-0349-2 T,P,HR,A, RPS Flow Sensor Foxboro (E-13 DH)
FT-0212 TP,H,R,A, RPS Pressure Transmitter Foxboro (E-11 GH)
PT-0212 TP,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9341 T,PH,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9351 T;P,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9361 T,P,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9371 T,P,H,RA, RPS Solenoid Valve ASCO (HT831665)
HY9342 T,P,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9352 T,P,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9362 T,P,HR,A, RPS Solenoid Valve ASCO (HT831665)
HY9372 TP,H,R,A, RPS Solenoid Valve ASCO (HT831665)
HY9433 TP,H,R,A, RPS Solenoid Valve ASCO (HT831665)
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model.#.
Component No.
Deficiency Solenoid Valve ASCO (HT831665)
TV-0221 TP,H,R,A, RPS Solenoid Valve ASCO (HT8320A108)
FY0306 T,P,H,R,A, RPS Solenoid Valve ASCO (HT8320A108)
HY-9316 T,P,H,RA, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-TV-0221 T,PH,R,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9341 T,PH,R,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9351 TP,HR,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9361 T,PH,R,A, RPS Limit Switch,,
NAMCO (EA-170)
ZSH & ZSL-HV-9371 T:,P,H,RA, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9342 T,P,H,R,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9352 T,P,HRA, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9362 T,P,H,R,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9372 T,PH,R,A, RPS Limit Switch NAMCO (EA-170)
HV-9433 T,P,H,R,A, RPS Limit Switch NAMCO (EA-170)
HV-9437 T,P,H,R,A, RPS Limit Switch NAMCO (EA-170)
ZSH & ZSL-FV0306 T,PH,RA, RPS.
Limit Switch NAMCO (EA-170)
ZSH & ZSL-HV-9316 TPH,R,A, RPS B-19
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #.
Component No.
Deficienc Motor Operated Valve Limitorque HV-9332 QT,A (SMB-1-40)
Motor Operated Valve Limitorque HV-9325 QT,A (SMB-1-40)
Motor Operated Valve Limitorque HV-9328 QT,A (SMB-1-40)
Motor Operated Valve Limitorque HV-9331 QT,A (SMB-1-40)
Motor Operated Valve Limitorque HV-9323 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9326 QTA (SMB-00-10)
Motor Operated Valve Limitorque HV-9329 Qf,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9332 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9324 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9327 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9330 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9333 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9367 QT,A (SMB'-00-10)
Motor Operated Valve Limitorque HV-9368 QT,A
-(SMB-00-10)
Motor Operated Valve Limitorque HV-9420 QT,A (SMB-00-10)
Motor Operated Valve Limitorque HV-9434
- QT,A (SMB-00-10)
B-20
APPENDIX B (Continued)
Equipment Manufacturer/
Description Model #
Component No.
Deficiency Motor Operated Valve Limitorque LV-0227B QT,A (SMB-00-10)
Motor Westinghouse P-015 QTA (5808 P39)
Motor Westinghouse P-016 QT,A (5808 P39)
Motor Westinghouse P-017 M(T),QT,A (5809)
Motor Westinghouse P-018 M(T),QT,A (5809)
Motor Westinghouse P-019 M(T),QT,A (5809)
Motor Westinghouse P-012 M(T),QT,A (5808 P39)
Motor Westinghouse P-013 1l(T),QT,A (5808 P39)
Motor Seimens-Allis P-020 M(T),QT,A Motor Seimens-Allis P-021 M(T),QT,A Solenoid Valve Target Rock HV-7816 QT,A (80B-001)
(A) Pump Motor Louis-Allis Pl90 M(T),QT,A (L-A Type)
(A) Pump Motor Louis-Allis P191 M(T),QT,A (L-A Type)
(A) Pump Motor Louis-Allis P192 M(T),QT,A (L-A Type)
(A) Hydro-Motor ITT General FV-0318 QT,A Operator (A) Hydro-Motor ITT General FV-0328 QT,A Operator (A) Audited Item B-21
APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable LEGEND:
Designation for Deficiency R -
Radiation T - Temperature QT - Qualification Time RT -
Required Time P -
Pressure H - Humidity CS - Chemical spray A - Material aging evaluation, replacement schedule, ongoing equipment surveillance S -
Submergence M - Margin I - HELB evaluation outside containment not completed QM - Qualification method RPN - Equipment relocation or replacement, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualification justification inadequate QI - Qualification information being developed RPS - Equipment relocation or replacement schedule provided Equipment Description Manufacturer Component No.
Deficiency (A) Connector Amphenol A
8KV Power Cable Anaconda (EP)
A 8KV Cable Termination Kit Raychem (HVT)
A Motor Connection Kit Raychem (HVCM-5)
A Heat Trace System Wire Thermon (TEK)
A (A) Heat Trace System-RTD Thermon A
Solenoid Valve ASCO (NP8320A187V) HY8200 A
Solenoid Valve ASCO (NP8320A187V) HY8201 A
Solenoid Valve ASCO (NP8320A187V) HY8202 A
(A) Audited item C-1
APPENDIX C (Continued)
Equipment Description Manufacturer Component No.
Deficiency Solenoid Valve ASCO (NP8320A187V) HY8203 A
Solenoid Valve ASCO (NP8320A187V) HY4057 A
Solenoid Valve ASCO (NP8320A187V) HY4058 A
Limit Switch NAMCO (EA-180)
ZSH-8200-2 A
Limit Switch NAMCO (EA-180)
ZSH-8201-1 A
Limit Switch NAMCO (EA-180)
ZSH-8202-2 A
Limit Switch NAMCO (EA-180)
ZSH-8203-1 A
Limit Switch NAMCO (EA-180)
ZSL-8200-2 A
Limit Switch NAMCO (EA-180)
ZSL-8201-1 A
Limit Switch NAMCO (EA-180)
ZSL-8202-2 A
Limit Switch NAMCO (EA-180)
ZSL-8203-1 A
Limit Switch NAMCO (EA-180)
ZSH-8419-1 A
Limit Switch NAMCO (EA-180)
ZSL-8421-2 A
Limit Switch NAMCO (EA-180)
ZSL-4057-2 A
Limit Switch NAMCO (EA-180)
ZSL-4058-1 A
Limit Switch NAMCO (EA-180)
ZSH-4057-2 A
Limit Switch NAMCO (EA-180)
ZSH-4058-1 A
Solenoid Valve Target Rock (75G)
HV0500 A
Solenoid Valve Target Rock (75G)
HV0502 A
Solenoid Valve Target Rock (75G)
HV7801 A
Solenoid Valve Target Rock (75G)
HV7802 A
Solenoid Valve Target Rock (75G)
HV7805 A
Solenoid Valve Target Rock (75G)
HV7806 A
Solenoid Valve Target Rock (75G)
HV9345 A
C-2
APPENDIX C (Continued)
Equipment Description Manufacturer Component No.
Deficiency Solenoid Valve Target Rock (75G)
HV9355 A
Solenoid Valve Target Rock (75G)
HV9365 A
Solenoid Valve Target Rock (75G)
HV9375 A
Solenoid Valve Target Rock (75G)
HV0296A A
Solenoid Valve Target Rock (75G)
HV0296B A
Solenoid Valve Target Rock (75G)
HV0297A A
Solenoid Valve Target Rock (75G)
HV0297B A
Solenoid Valve Target Rock (75G)
HV0298 A
Solenoid Valve Target Rock (75G)
HV0299 A
Solenoid Valve Target Rock (75G)
HV8248 A
Solenoid Valve Target Rock (75G)
HV8249 Motor Operated Valve Limitorque HV4713 A
(SMB-000-2)
Solenoid Valve Valcor HV9398 A
(V-5260-573-1)
Solenoid Valve Valcor HV9399 A
(V-5260-573-1)
C-3
APPENDIX D Safety-Related Systems List1 Function System Emergency Reactor Shutdown Safety injection system Chemical and volume control system Auxiliary feedwater system Reactor protection, system Engineered safety features actuation system Containment Isolation Containment isolation system Engineered safety features actuation system Reactor Core Cooling Safety injection system Containment Heat Removal Containment spray system Containment atmosphere emergency cooling Salt water cooling system Component cooling water system Engineered safety features actuation system Core Residual Heat Removal Salt water cooling system Component cooling water system Auxiliary feedwater system Shutdown cooling system Prevention of Significant Containment spray system Release of Radioactive Containment isolation system Material to Environment Combustible gas control system Engineered safety features actuation system Radiation monitoring system Support Systems Emergency operation HVAC system Diesel Generator System a
Radiation monitoring system Post-accident monitoring system Reactor-coolant gas vent
'The NRC staff recognizes that there are differences in nomenclature of systems because of plant vintage and engineering design; consequently, some systems performing identical or similar functions may have different names. In those instances, it was necessary to verify the function of the system(s) with the responsible IE regional reviewer and/or the licensee.
D-1
ENCLOSURE 3 STATUS OF STAFF REVIEW OF II.F.2, INADEQUATE CORE COOLING (ICC) INSTRUMENTATION (1) The staff has concluded that the interim backup display system for the core exit thermocouples is acceptable for operation prior to January 1982.
After January 1982, the backup core exit thermocouple display system and other existing ICC instrumentation.must meet the requirements of NUREG-0737.
(2) The staff has developed a number of questions relating to the details of the final ICC instrumentation system. These are given in Enclosure 4, We request that you provide responses to these items by September 1, 1981.
(3) The reactor vessel level instrumentation.proposed by the applicant must be installed on a schedule which will permit the instrumentation to be made operational for purposes of calibration during the first operating cycle.
ENCLOSURE 4 REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSEL LEVEL INSTRUMENTATION
- 1. In the discussion of a suitable definition of Inadequate Core Cooling, the definition is constrained to fall within bounds of certain core conditions. Please discuss your approach to defining "inadequate core cooling". What are the limiting conditions for-the applicability of the heated junction thermocouple level system?
2., Identify the maximum size break for which the system will still allow the operator to take corrective action under ICC procedures. Please include a discussion of the response capabilities of the heated junction thermoucouple instrumentation with respect to the system dynamics.
These questions should be answered for a small break, such as 3 inch.
- 3. Describe the Phase II test program, or programs used in the evaluation of the heated junction thermocouple level measurement system. Please provide representative test results including any anomalous results, Explain the results with respect to expected behavior in operating reactors.
- 4. Discuss the survivability and outputs of the heated junction level measurement system during and after a large break LOCA and.support with test results.
- 5. Provide an analysis to determine if voiding can occur in.the core of a CE reactor while the upper head is still filled with water. Discuss the extent of voiding which can occur and whether or not it can lead to inadequate core cooling. Please analyze the effect on the core exit thermocouples should such an event occur and discuss how inadequate core cooling conditions would be determined under these conditions.
There is experimental evidence that this can occur, i.e., in tests SUT-2 (10% break), SUT-5 (2.5% break), SUT-7 (5% breakl. At Semi scale, these effects were observed.
- 6. Discuss the expected response of the heated thermocouple level sensors during a repressurization with the water level below the sensor and the possible effects of condensation on the response of the sensors.
Could this sequence of events lead to an indication which would imply that the sensor is covered when it is not? Please provide representative test data.
ENCLOSURE 4
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- 7. Discuss the expected time response of the system with respect to the individual components and as a whole.
Identify and discuss the factors which limit the time response.
- 8. No specific information has been given for the spacing of the sensors in each heated junction thermocouple instrument string. Are the sensors to be spaced evenly from the core allignment plate to the top of the reactor vessel head? Discuss the spacing chosen. Will the spacing be the same in both instrument strings? If not, how wonld the decrease in resolution due to the loss of a single sensor affect the ability of the system to detect an approach to inadequate core cooling?
(i.e.,
how is the redundancy of the system affected if dissimilar spacings are used in the two detector strings?).
- 9. Discuss how the core-exit thermocouples might be used to estimate the depth of core uncovery. Also discuss how the rate of loss of coolant may affect the core-exit thermocouple response. Provide an evaluation of the pro's and con's of using the indications of the core-exit thermocouples as a measure of the liquid inventory. In the vessel if the coolant level is below the top of the core..
- 10. Discuss the expected behavior of the level sensor shroud surrounded by a high velocity two-phase mixture. In particular, discuss how the system is protected from the effects of high velocity steam entering the bottom ports of the shroud and creating a two phase mixture within the shroud. If restrictions are placed in the bottom of the shroud to block the bottom drain paths, discuss or show experimental evidence that there is still adequate drainage and response time.
- 11.
Describe the choice of heater power or range of heater powers to be used with the heated junction thermocouple sensors, Describe the heater power supply or heater power control system. Are separate supplies provided for each sensor heater? Discuss the heater supply system with respect to NUREG 0737 "single failure" criterion. Discuss how uncovered sensors are protected from overheating while covered sensors are supplied with sufficient power for a clear indication of uncovery. Will AC or DC power be used? Discuss the possible effects of leakage, particularly at high temperatures on the level measurement with both AC and DC heater power. Discuss the possible effects of AC pick-up on the instrumentation system.
ENCLOSURE 4
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- 12.
Describe the on-line test procedures for the heated junction thermocouple sensors. One test mentioned is based on a change in indication, observed by varying heater power. Discuss how the operator or person testing the system will decide that the sensors are operating. i.e., how much temperature change would be expected for a given power change?
Discuss the effectiveness of the test procedures under various reactor conditions. i.e., cold shutdown, futll power, and post accident.
- 13.
Describe how the operational availability will be determined. What criteria are used? describe the servicing, testing and calibration programs.
- 14.
Describe how the processor tests operate to determine that the sensor outputs are within range. How are the ranges selected?
- 15.
Describe the display measurement units.
- 16.
Describe which parameter or parameters would need to be calculated from the sensor inputs. The description of the QSPDS implies that such a calculation might or might not be required. When would it be required? When would it not be required?
- 17.
Specifically, describe the automatic on-line surveillance tests.
- 18. Describe the manual on-line diagnostic capability and procedures.
- 19. Discuss the predetermined setpoint for the heated junction thermocouple signals and how it will be selected.
ENCLOSURE 5 SECOND AND LATER CYCLE POWER DISTRIBUTIONS The Standard Format and Content of Safety Analysis Reports, Regulatory Guide 1.70, states that in Chapter 4 of the SAR
"...the applicant should provide an evaluation and supporting information to establish the capability of the reactor to perform its safety functions throughout its design lifetime under all normal operation modes..."
Are the analyses presented in Section 4.4 representative of the initial core only or have future cycles been analyzed? Provide a discussion of how power distributions for future cycles are considered in the FSAR analyses.
Is there any assurance that San Onofre 2 and 3 can operate at the licensed power level without excessive DNB trips throughout future cycles? Will revisions to the design methodology be required in order to maintain sufficient thermal margin?
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