ML18095A330
| ML18095A330 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 07/02/1990 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NLR-N90115, NUDOCS 9007090325 | |
| Download: ML18095A330 (37) | |
Text
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Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations JUL o 2 1990 NLR-N90115 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
GENERIC LETTER 90-04 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES SALEM UNITS 1 AND 2 AND HOPE *CREEK GENERATING STATION DOCKET NOS. 50-272, 50-311 AND 50-354 On April 25, 1990, the Nuclear Regulatory Commission (NRC) issued Generic Letter 90-04, requesting current information on the implementation status of specified generic safety issues (GSis).
PSE&G hereby provides its response to Generic Letter 90-04 for Salem Units 1 and 2 and Hope Creek Generating Station.
The information requested in Generic Letter 90-04 is contained in 2 attachments to this submittal; Attachment 1 pertains to Salem Units 1 and 2, and Attachment 2 pertains to Hope Creek.
Should you have any questions regarding this transmittal, please feel free to contact us.
Thank you.
Affidavit Attachments (2)
Sincerely,
~-1
,I STATE OF NEW JERSEY COUNTY OF SALEM
)
)
)
Ref:
NLR-N90094 SS.
S. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth on our letter dated concerning Salem Units 1 and 2 and Hope Creek Generating Station, are true to the best of my knowledge, information and belief.
7 Subscribed and Sworn~ore me this d:i day of ~
, 1990
(
My Commission expires on sey SUZANNE V. PHILLIPS Notary Public oi New Jersey My Commission Expires Feb. 14, 1994
' i
Document Control Desk NLR-N90115 JUL 0 2 1990 c
Mr. J. c. Stone Licensing Project Manager Mr. c. Y. Shiraki Licensing Project Manager Mr. T. P. Johnson Senior Resident Inspector Mr. T. T. Martin Administrator -
Region 1 Mr. Kent Tosch Chief -
New Jersey Department of Environmental Protection Division of Environmental.Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
- .\\.
NLR-N9oi15 ATTACHMENT 1 SALEM UNITS 1 AND 2 -
DOCKET NOS. 50-272 AND 50-311 RESPONSE TO GENERIC LETTER 90-04 STATUS OF IMPLEMENTATION OF GENERIC SAFETY ISSUES
L FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/
CMPA NO.)
40 (B065)
GSI/
CMPA NO.)
41 (BOSS)
TITLE Safety Concerns associated with pipe breaks in the BWR Scram systems COMMENT None TITLE BWR scram discharge volume systems COMMENT None Page 1 of 19 APPLICABLE STATUS NO NA APPLICABLE
- STATUS NO NA
~/
~
43 (B107)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Reliability of air systems YES I
COMMENT PSE&G LETTER TO NRC/NLR-N88188 (12/6/88) - Request for extension of the GL 88-14 response submittal due date for Salem and Hope Creek stations.
The original due date of 2/8/89 was revised to 3/31/89 for Salem Units 1 and 2 and 6/30/89 for Hope Creek.
PSE&G LETTER TO NRC/NLR-N89062 (3/31/89) -
GL 88-14 response submittal for Salem Units 1 and 2.
The response to Item 2 states that although applicable maintenance procedures are adequate to address the concerns of GL 88-14, they will continue to be reviewed and upgraded over the next several years.
The response to Item 3 consists of several open action items in the form of required testing.
The tests discussed in the response have been completed for both units.
A final report has been prepared and submitted for approval; it will be submitted to the NRC by 7/27/90.
Page 2 of 19
~
51 (L913)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Improving the reliability of open-cycle service water systems Yes I
COMMENT PSE&G LETTER TO NRC/NLR-N90021 (1/26/90) -
GL 89-13 response submittal for Salem Units 1 and 2 and Hope Creek.
Letter contains a summary of commitments and schedules for the completion of several open action items.
The proposed implementation date for Salem Unit 1 action items is October, 1990 and for Unit 2, November, 1991; these items consist of the following:
Item 1 Item 2 Item 3 Item 4 Item 5 Develop/revise inspection procedures for the Intake structure and Emergency Air Compressor dead-leg.
Oevelop and implement the inspection program and Service Water Heat Exchanger Performance program.
Generate required inspection procedures and/or work standards.
Confirm the ability of the Service Water system to a perform as required in the event of a single active component failure.
Implement procedure generation/modification as necessary to support Items 1 through 3
- Page 3 _of 19
I NO.
67.3.3 (A017)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Improved accident monitoring Yes c
COMMENT PSE&G LETTER TO NRC (4/2/81) - Contains an initial evaluation of Salem Unit 2 to determine the degree of compliance with Regulatory Guide 1.97 and a schedule for bringing the unit into compliance.
PSE&G LETTER TO NRC (04/15/83) -
GL 82-33 response submittal for Salem Units 1 and 2.
PSE&G LETTER TO NRC (06/01/83) - Update of GL 82-33 response submittal for Salem Units 1 and 2.
PSE&G LETTER TO NRC (9/21/83) - Response to a RAI dated 7/26/83.
PSE&G LETTER TO NRC C8/9/84) - Addresses 18 items that were identified by Idaho National Engineering Laboratory in an interim report as deviating from the guidance of Regulatory Guide 1.97
- Page 4 of 19
,---------------------~--
I NO.
75 (B076)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 1.1 - Post-trip Review (program description and procedure)
COMMENT APPLICABLE Yes STATUS c
PSE&G LETTER TO NRC {7/22/83) -
Salem response submittal.
References letters dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83.
PSE&G LETTER TO NRC (8/2/85) - Supplemental information pertaining to this item.
NRC LETTER {9/12/85) - Contains SER and acceptance of response for this item.
Referencees PSE&G letters dated 7/22/83 and 8/2/85
- Page 5 of 19
I NO.
75 (BOSS)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 1.2 - Post-trip review -
Data and information capability COMMENT APPLICABLE Yes STATUS c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
Briefly describes sequence of events recorder.
PSE&G LETTER TO NRC (11/7/83) -
Supplemental Salem response submittal.
Provides a detailed description of the sequence of events recorder.
NRC LETTER (12/5/85) - Draft technical evaluation report.
States that the Salem response to Item 1.2 is incomplete.
References PSE&G letters dated 7/22/83 and 11/7/83.
PSE&G LETTER TO NRC (1/20/86) technical evaluation report.
conference held between PSE&G NRC on 1/10/86
- Salem response to Draft Documents telephone and Mr. Joel Kramer of the Page 6 of 19
NO.
75 (B077)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Item 2.1 -
Equipment classification and vendor interface (reactor trip system components)
COMMENT Yes c
PSE&G LETTER TO NRC (3/8/83) - Provides PSE&G's position on issues related to the Salem Reactor Trip Breaker Failures.
PSE&G LETTER TO NRC (3/14/83) -
Provides information on the Salem Q-List and Master Equipment List.
PSE&G LETTER TO NRC (4/7/83) - Corrective action program related to the Reactor Trip Breaker failures.
PSE&G LETTER TO NRC (4/8/83) -
Supplement to the corrective action program.
PSE&G LETTER TO NRC (04/28/83) - Corrective action summary for Salem Units 1 and 2.
References PSE&G letter dated 04/08/83
- NRC CONFIRMATORY ORDER (05/06/83) -
Confirms PSE&G commitments made in 04/28/83 letter.
PSE&G LETTER TO NRC (5/31/83) - Transmittal of Beta Corporation final report on the corrective action program.
NRC LETTER (03/18/86) - States that the terms of the 05/06/83 Confirmatory Order have been satisfactorily completed.
NRC LETTER (8/25/86) -
Contains SER and acceptance of Salem Unit 1 and 2 response for Part 1.
References PSE&G letters dated 3/8/83, 3/14/83, 4/7/83, 4/8/83, and 5/31/83.
NRC LETTER (1/6/89) -
Contains SER and acceptance of Salem Unit 1 and 2 response for Part 2.
References PSE&G letters dated 3/8/83 and 3/14/83
- Page 7 of 19
75 (B086)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Item 2.2.1 -
Equipment Classification for Safety-Related Components COMMENT Yes c
PSE&G LETTER TO NRC (04/28/83) - Corrective action summary for Salem Units 1 and 2.
References PSE&G letter dated 04/08/83.
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
NRC CONFIRMATORY ORDER (05/06/83) -
Confirms PSE&G commitments made in 04/28/83 letter.
PSE&G LETTER TO NRC (9/20/85) - Response to RAI dated 7/22/85.
NRC LETTER (03/18/86) - States that the terms of the 05/06/83 Confirmatory Order have been satisfactorily completed.
PSE&G LETTER TO NRC (4/17/89) - Response to RAI documenting a telephone conversation that took place on 3/30/89.
Describes the transfer from Bechtel's Master Equipment List to PSE&G's Managed Maintenance Information System.
NRC LETTER (8/31/89) - Contains SER and acceptance of Salem Unit 1 and 2 response to Item 2.2.1.
References PSE&G letters dated 7/22/83, 9/20/85 and 4/17/89
- Page 8 of 19
FACILITY NAME: SALEM UNITS 1 AND 2
.)
DOCKET NOS.:
50-272 AND 50-311 75 (L003)
GSI/
NO.
078)
LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Item 2.2.2 - Vendor Interface for Safety-Related Components COMMENT Yes E
PSE&G LETTER TO NRC (04/28/83) - Corrective action summary for Salem Units 1 and 2.
References PSE&G letter dated 04/08/83.
NRC CONFIRMATORY ORDER (05/06/83) -
Confirms PSE&G commitments made in 04/28/83 letter.
NRC LETTER (03/18/86) - States that the terms of the 05/06/83 Confirmatory Order have been satisfactorily completed.
This item is being re-evaluated in response to GL 90-03.
PSE&G's response will be submitted September, 1990.
TITLE APPLICABLE STATUS Items 3.1.1 & 3.1.2 - Post-Maintenance Testing ( Reactor Trip System Components )
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 3/S/83, 3/14/83, 4/7/83 and 4/8/83.
PSE&G LETTER TO NRC (11/7/83) - Supplemental Salem response submittal.
NRC LETTER (3/17/86) -
Contains SER and acceptance of Salem Unit 1 and 2 response
- Page 9 of 19
I NO.)
75 (B079)
~
75 (B087)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Item 3.1.3 -
Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83.
PSE&G LETTER TO NRC (11/7/83) -
Supplemental Salem response submittal.
PSE&G LETTER TO NRC (9/20/85) - Response to RAI dated 7 /22/85.
NRC LETTER (12/6/85) - Contains SER and acceptance of Salem Units 1 and 2 response to this item.
References PSE&G letters dated 7/22/83, 11/7/83, and 9/20/85.
TITLE APPLICABLE STATUS Items 3.2.1 & 3.2.2 - Post-Maintenance Testing (All Other Safety-Related Components)
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83.
PSE&G LETTER TO NRC (11/7/83) - Supplemental Salem response submittal.
NRC LETTER (3/17/86) - Contains SER and acceptance of Salem Unit 1 and 2 response.
Page 10 of 19
I NO.
75 (B088)
I NO.
75 (BOSO)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Item 3.2.3 -
Post-Maintenance Testing-Changes to Test Require-ment (All Other Safety-Related components)
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) - Salem response submittal.
References letter dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83 although Item 3.2.3 is not specifically mentioned.
PSE&G LETTER TO NRC (11/7/83) - Supplemental Salem response submittal.
PSE&G LETTER TO NRC (9/20/85) - Response to RAI dated 7/22/85.
NRC LETTER (12/6/85) - Contains SER and acceptance of Salem Units 1 and 2 response to this item.
References PSE&G letters dated 7/22/83, 11/7/83, and 9/20/85.
TITLE APPLICABLE STATUS Item 4.1 ~ Reactor Trip System Reliability (Vendor-Related Modifications)
COMMENT Yes c
PSE&G LETTER TO NRC (04/08/83) - states that all modifications identified by Westinghouse were implemented for both units.
PSE&G LETTER TO NRC (7/22/83) - Salem response submittal.
References letter dated 4/7/83 and 4/8/83.
NRC LETTER (3/17/86) - Contains SER and acceptance of Salem Unit 1 and 2 response.
Page 11 of 19
L 75 (B081)
GSI/
CMPA NO.)
75 (B082)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NQS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Items 4.2.1 & 4.2.2 - Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) - Salem response submittal.
References letter dated 3/8/83, 3/14/83, 4/7/83,4/8/83 and 5/31/83.
PSE&G LETTER TO NRC (8/19/85) - Response to RAI dated 6/17/85.
PSE&G LETTER TO NRC (9/20/85) - Response to RAI dated 7/22/85.
NRC LETTER (12/6/85) - Contains SER and acceptance of Salem Units 1 and 2 response to these items.
References PSE&G letters dated 7/8/83 and 8/19/85.
TITLE.
APPLICABLE STATUS Item 4.3 - Reactor Trip System Reliability -
Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
COMMENT Yes c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 7/15/83.
PSE&G LETTER TO NRC (3/14/84) - Plant specification information on RPS Shunt Trip modification.
PSE&G LETTER TO NRC (6/7/84) - Additional information pertaining to plant modification.
NRC LETTER (6/25/84) -
SER and acceptance of Salem Unit 1 and 2 response and plant modifications.
Page 12 of 19
I NO.
75 (B090)
GSI/
(MPA NO.)
75 (B091)
GSI/
(MPA NO.)
75 (B092)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 4.3 - Reactor Trip System Reliability - Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B&W Plants)
COMMENT APPLICABLE Yes STATUS c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 7/15/83.
PSE&G LETTER TO NRC (10/17/85) -
Salem Unit 1 and 2 license change request (LCR 84-14).
Change was granted under Amendments 97 for Unit 1 and 74 for Unit 2.
TITLE Item 4.4 - Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
COMMENT None TITLE Item 4.5.1 - Reactor Trip system Reliability-Diverse Trip Features (System Functional Testing)
COMMENT APPLICABLE STATUS No NA APPLICABLE STATUS Yes c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal *.
References letter dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83 and LCR 83-08.
Change was granted under Amendment 59 for Unit 1 and 28 for Unit 2.
NRC LETTER (3/17/86) - Contains SER and acceptance of Salem Unit 1 and 2 response.
Page 13 of 19
75 (B093)
GSI/
CMPA NO.)
86 (B084)
FACILITY.NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Items 4.5.2 & 4.5.3 - Reactor Trip System Reliability Test Alterna-tives and Intervals (System Functional Testing)
COMMENT APPLICABLE Yes STATUS c
PSE&G LETTER TO NRC (7/22/83) -
Salem response submittal.
References letter dated 3/8/83, 3/14/83, 4/7/83 and 4/8/83 and LCR 83-08.
Change was granted under Amendment 59 for Unit 1 and 28 for Unit 2.
PSE&G LETTER TO NRC (10/16/85) - Response to RAI dated 7/22/85.
NRC LETTER (3/10/89) - Contains SER and acceptance of Salem Unit 1 and 2 response for Item 4.5.2.
References PSE&G letter dated 7/22/83.
NRC LETTER (5/26/89) - Contains SER, contractor's report, and acceptance of Salem Unit 1 and 2 response for Item 4.5.3.
References PSE&G letters dated 7/22/83 and 10/16/85.
TITLE Long Range Plan for Dealing with Stress Corrosion cracking in BWR Piping COMMENT None Page 14 of 19 APPLICABLE STATUS No NA
.,0.)
93 (B098)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE steam Binding of Auxiliary Feedwater Pumps COMMENT APPLICABLE Yes NLR-N88078 (5/27/88) - Salem Unit 1 and 2 response submittal.
Supplies requested information
- Page 15 of 19 STATUS c
~
99 (L817)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS RCS/RHR Suction Line Valve Interlock on PWRs COMMENT Yes I
NLR-N89001 Cl/6/89) - Initial PSE&G response submittal.
NLR-N89199 (1/23/89) - Request for deferral of planned modifications.
NLR-N89014 Cl/27/89) -
90 day response submittal.
Committed to have all enhancements completed by Unit 1, 9th and Unit 2, 5th refueling outages.
NRC LETTER TO PSE&G (7/5/89) -
Comments/closeout of PSE&G's responses.
Remaining open items to be completed by 10/30/90 for Unit 1 and 11/21/90 for Unit 2.
These items consist of:
- 1.
Convert tygon tubing level indication into hard-pipe system *
- 2.
Provide visual indication of abnormal level, temperature or DHR system performance on SPDS.
- 3.
Evaluate the need for an audible alarm for the DHR monitoring system.
Page 16 of 19
124 I
NO.
GSI/
(MPA NO.)
A-13 (B017)
GSI/
(MPA NO.)
A-13 (B017)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Auxiliary Feedwater System Reliability COMMENT None TITLE Snubber Operability Assurance -
Hydraulic Snubbers COMMENT APPLICABLE No APPLICABLE Yes STATUS NA STATUS c
NRC LETTER TO ALL POWER REACTOR LICENSEES (11/20/80) -
Required technical Specification revisions for snubber surveillances.
PSE&G REQUEST FOR AMENDMENTS TO SALEM LICENSES (8/10/81)
- Requested the changes required by the NRC letter of 11/20/80.
Requested changes were issued as Amendment 40 for Unit 1 and Amendment 5 for Unit 2 on 2/2/82.
TITLE Snubber Operability Assurance -
Mechanical Snubbers COMMENT APPLICABLE STATUS Yes c
NRC LETTER TO ALL POWER REACTOR LICENSEES (11/20/80) -
Required technical Specification revisions for snubber surveillances.
PSE&G REQUEST FOR AMENDMENTS TO SALEM LICENSES (8/10/81)
- Requested the changes required by the NRC letter of 11/20/80.
Requested changes were issued as Amendment 40 for Unit 1 and Amendment 5 for Unit 2 on 2/2/82.
Page 17 of 19
)
I NO.
A-16 (D012)
GSI/
(MPA NO.)
A-35 (B023)
GSI/
CMPA NO.)
B-10 FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-311 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Steam Effects on BWR Core Spray Distribution COMMENT None TITLE Adequacy of Offsite Power Systems
- COMMENT APPLICABLE No APPLICABLE Yes STATUS NA STATUS c
PSE&G LETTER TO NRC (9/13/79) -
Describes proposed design change related to undervoltage protection.
PSE&G LETTER TO NRC (10/10/79) -
Salem Unit 1 and 2 response to to NRC letter dated 08/08/79.
Contains all requested information and discusses actions taken.*
PSE&G LETTER TO NRC (3/3/80) - Provides information on degraded grid voltage protection in response to questions asked at a meeting that took place 10/25/79.
NRC LETTER (1/19/81) -
SER and acceptance of Salem design modifications.
References PSE&G letters dated 8/1/77, 9/13/79 and 3/3/80 and a meeting that took place between PSE&G and the NRC on 10/25/79.
PSE&G LETTER TO NRC (6/16/81) -
LCR 81-08 for Salem Units 1 and 2.
License change was granted on 7/23/82 as Amendment 45 for Unit 1 and 10 for Unit 2.
TITLE Behavior of BWR Mark III Containments COMMENT None Page 18 of 19 APPLICABLE STATUS No NA
~-------
B-36
_/
GSI/
l
_)
CMPA NO.)
B-63 (B045)
FACILITY NAME: SALEM UNITS 1 AND 2 DOCKET NOS.:
50-272 AND 50-3ll LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Develop Design, Testing and Maintenance Criteria for Atmospheric Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems COMMENT None TITLE Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary COMMENT APPLICABLE No APPLICABLE Yes STATUS NA STATUS c
PSE&G LETTER TO NRC (03/14/80) -
Salem Unit 1 response to NRC letter dated 02/23/80.
NRC LETTER (04/20/81) - Order for modification of Unit 1 license concerning primary coolant system pressure isolation valves.
The modification to Technical Specifications changed Index page IV and added pages 16a, b, and c (still in effect) creating LCO 3.4.6.3.
The new LCO addressed pressure isolation valves as they pertained to reactor coolant system leakage.
The requirements of the Order for modification described above were satisfied for Unit 2 by incorporating the respective items into LCO 3.4.7.2, item f and Table 3.4-1 (including associated action statements and surveillances) of the original Technical Specifications issued in 4/18/80.
Page 19 of 19
_)
NLR-N90115 ATTACHMENT 2 HOPE CREEK GENERATING STATION -
DOCKET NO. 50-354 RESPONSE TO GENERIC LETTER 90-04 STATUS OF IMPLEMENTATION OF GENERIC SAFETY ISSUES
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/
CMPA NO. l 40 (B065)
GSI/
(MPA NO.)
41 (BOSS)
TITLE Safety Concerns associated with pipe breaks in the BWR Scram systems COMMENT APPLICABLE STATUS Yes c
GL 81-35 was not resolved to the commission's satisfaction prior to issuance of the Hope Creek SER.
The NRC therefore imposed License Condition 2 (SER Section 4.6) to track implementation of the generic letter.
PSE&G LETTER TO NRC (03/24/86) -
Hope Creek response to NUREG-0803 (GL 81-35).
Transferred the necessary commitments from the license to the FSAR.
The commitments associated with GL 81-35 consisted of 4 action items which were entered into the PSE&G Action Tracking System and subsequently closed out upon completion.
There were no actions required to be taken in response to GL 86-01.
TITLE BWR scram discharge volume systems COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
Page 1 of 13
I NO.
43 (B107)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Reliability of air systems YES c
COMMENT NLR-N88188 (12/6/88) - Request for extension of the GL 88-14 response submittal due date for Salem and Hope creek Stations.
The original due date of 2/8/89 was revised to 3/31/89 for Salem Units 1 and 2 and 6/30/89 for Hope Creek.
NLR-N89119 (06/29/89)
GL 88-14 response submittal for Hope Creek.
The response to Item 3 consists of an open action item; loss of Instrument Air tests were to be performed during the second refueling outage that began in September of 1989.
The open item was entered into the PSE&G Action Tracking System and subsequently closed out upon completion of the required tests on 12/29/89.
Page 2 of 13
j
.:i I
NO.
51 (L913)
GSI/
(MPA NO.)
67.3.3 (A017)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE STATUS Improving the reliability of open-cycle service water systems Yes I
COMMENT NLR-N90021 (1/26/90) -
GL 89-13 response submittal for Salem Units 1 and 2 and Hope Creek.
Several open action items are delineated in the response.
The letter contains a summary of commitments and schedules for Salem and Hope Creek plants.
The proposed implementation dates for Hope Creek action items are as follows:
Item 1 Item 2 Item 3 Item 4 Item 5 Develop/revise work standards for intake structure inspection in March, 1991.
Make instrumentation modifications on the "B" Service Water loop in March, 1991 and on the "A" loop in October, 1992.
Begin the formalized routine inspection program on the "B" loop in March, 1991 and on the "A" loop in October, 1992.
Incorporate additional inspection work standards into the recurring task database in March, 1991.
Complete reviews to ensure the Service Water systems' ability to perform as required in the event of a single active component failure in March, 1991.
Complete procedure generation/modification to support Items 1 through 3 above in March,1991.
TITLE APPLICABLE STATUS Improved accident monitoring Yes NC COMMENT 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986
- Page 3 of 13
j
,J
~
75 (B076)
GSI/
(MPA NO.)
75 (B085)
I (MPA NO.)
75 (B077)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 1.1 - Post-trip Review (program description and procedure)
COMMENT APPLICABLE Yes STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Item 1.2 - Post-trip review -
Data and information capability COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE APPLICABLE STATUS Item 2.1 - Equipment classification Yes NC and vendor interface (reactor trip system components)
COMMENT 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
Page 4 of 13
1 I
NO.)
75 (B086)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE APPLICABLE Item 2.2.1 -
Equipment Classification Yes for Safety-Related Components COMMENT STATUS c
PSE&G LETTER TO NRC (3/30/84) -
Hope Creek response submittal.
Describes PSE&G's program identifying and classifying safety related components.
Specifies actions to be completed by 9/84.
PSE&G LETTER TO NRC (12/17/84) - Revision 1 of Hope Creek response submittal.
Provided supplemental information to 3/30/84 letter.
NRC LETTER (3/19/85) -
RAI PSE&G LETTER TO NRC (5/21/85) - Response to 3/19/85 RAI.
NLR-N89181 (09/08/89) - Additional information on Item 2.2.1 updating response of 05/21/85.
Describes the transfer from Bechtel's Master Equipment List to PSE&G's Managed Maintenance Information System.
NLR-N89195 (10/11/89) - Additional information on Item 2.2.1.4.
NRC DOCKET 50-354 LETTER (11/15/89) -
SER and technical evaluation report on the Hope Creek response submittal.
Concludes that the response is acceptable.
Page 5 of 13
~
75 (L003) 078)
GSI/
(MPA NO.)
75 (B079)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 2.2.2 - Vendor Interface for Safety-Related Components COMMENT APPLICABLE Yes STATUS E
PSE&G LETTER TO NRC (3/30/84) -
Hope Creek response submittal.
Refers to response to Item 2.1.
PSE&G LETTER TO NRC (12/17/84) - Revision 1 of Hope Creek response submittal.
Provided supplemental information to 3/30/84 letter.
NRC LETTER (3/19/85) -
RAI PSE&G LETTER TO NRC (5/21/85) - Response to 3/19/85 RAI.
This item is being re-evaluated in response to GL 90-03.
PSE&G's response will be submitted September, 1990.
TITLE Items 3.1.1 & 3.1.2 - Post-Maintenance Testing ( Reactor Trip System Components )
COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Item 3.1.3 -
Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
Page 6 of 13
1
\\.
I NO.)
75 (B087)
GSI/
(MPA NO.)
75 (B088)
GSI/
(MPA NO.)
75 (BOSO)
_,\\
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Items 3.2.1 & 3.2.2 - Post-Maintenance Testing (All Other Safety-Related Components)
COMMENT APPLICABLE Yes STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Item 3.2.3 -
Post-Maintenance Testing-Changes to Test Require-ment (All Other Safety-Related Components)
COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications)
COMMENT None Page 7 of 13 APPLICABLE STATUS No NA
I.
-~
l.,
I NO.
75 (B081)
GSI/
(MPA NO.)
75 (B082)
GSI/
(MPA NO.)
75 (B090)
Jo FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Items 4.2.1 & 4.2.2 - Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
COMMENT None TITLE Item 4.3 - Reactor Trip System Reliability -
Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
COMMENT None TITLE Item 4.3 - Reactor Trip System Reliability - Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B&W Plants)
COMMENT None Page 8 of 13 APPLICABLE No APPLICABLE No APPLICABLE No STATUS NA STATUS NA STATUS NA
~
~*
I NO.
75 (B091)
GSI/
CMPA NO.)
75 (B092)
GSI/
(MPA NO.)
75 (B093)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Item 4.4 - Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
COMMENT None TITLE Item 4.5.1 - Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)
COMMENT APPLICABLE No APPLICABLE Yes STATUS NA STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Items 4.5.2 & 4.5.3 - Reactor Trip System Reliability Test Alterna-tives and Intervals (System Functional Testing)
COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986
- Page 9 of 13
Ir, l
_)
~
86 (B084)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Long Range Plan for Dealing with stress Corrosion cracking in BWR Piping COMMENT APPLICABLE Yes STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986
- Page 10 of 13
u '
\\,
~
I NO.
93 (B098)
GSI/
CMPA NO.)
99 (L817)
GSI/
NO.
GSI/
CMPA NO.)
j_
A-13 (B017)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Steam Binding of Auxiliary Feedwater Pumps COMMENT None TITLE RCS/RHR Suction Line Valve Interlock on PWRs COMMENT None TITLE Auxiliary Feedwater System Reliability COMMENT None TITLE Snubber Operability Assurance -
Hydraulic Snubbers COMMENT APPLICABLE No APPLICABLE No APPLICABLE No APPLICABLE Yes STATUS NA STATUS NA STATUS NA STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
Page 11 of 13
~
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_)...
A-13 (B017)
GSI/
(MPA NO.)
A-16 (D012)
A-35 (B023)
GSI/
(MPA NO.)
B-10 FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Snubber Operability Assurance -
Mechanical Snubbers COMMENT APPLICABLE Yes STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Steam Effects on BWR Core Spray Distribution COMMENT None TITLE Adequacy of Offsite Power Systems COMMENT APPLICABLE STATUS No NA APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Behavior of BWR Mark III Containments COMMENT None Page 12 of 13 APPLICABLE STATUS No NA
- ,J
)..
B-36 I
NO.
GSI/
(MPA NO.)
B-63 (B045)
FACILITY NAME: HOPE CREEK GENERATING STATION DOCKET NO.:
50-354 LICENSEE:
PUBLIC SERVICE ELECTRIC AND GAS TITLE Develop Design, Testing and Maintenance Criteria for Atmospheric Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems COMMENT APPLICABLE Yes STATUS NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986.
TITLE Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary COMMENT APPLICABLE STATUS Yes NC 5% Facility Operating License issued on April 11, 1986.
100% Facility Operating License issued on July 25,1986
- Page 13 of 13