ML18094B185
| ML18094B185 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek, 05000000 |
| Issue date: | 11/30/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-89-21, NLR-N89230, NUDOCS 8912070005 | |
| Download: ML18094B185 (13) | |
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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer
(
I NOV 3 0 1989 NLR-N89230 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. c. 20555 Gentlemen:
STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE REQUIREMENTS NRC GENERIC LETTER 89-21 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311, AND 50-354 Public Service Electric and Gas Company {PSE&G) hereby provides a response to your October 19, 1989 letter requesting information concerning the implementation status of Unresolved Safety Issue
{USI) requirements.
We have researched appropriate files and provide the attached tables identifying the status of all USis, for which a final technical resolution has been achieved and which are applicable to the Salem Generating Station {Table 1) and Hope Creek Generating Station {Table 2).
Mr. J. Stone {NRC Project Manager for SGS) has assisted our effort by reviewing NRC files for significant USI correspondence between PSE&G and the NRC staff for the SGS.
The enclosed tables summarize the results of our investigation and provide specific information related to current USI status, including a reference to any supporting documentation.
Please contact us if you have any questions regarding this transmittal.
Sincerely, Enclosures llo;:P (L',11
Document Control Desk NLR-N89230 c
Mr. J. c. stone 2
Licensing Project Manager - Salem Ms. K. Halvey Gibson Senior Resident Inspector - Salem Mr. c. Y. Shiraki
- 9 Licensing Project Manager - Hope Creek Mr. D. K. Allsopp Senior Resident Inspector - Hope Creek Mr. W. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 NOV 3 O 1989
USI NO.
A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 Table 1 STATUS OF UNRESOLVED SAFETY ISSUES FOR SALEM TITLE APPLICABILITY STATUS water Hammer Yes C
Asymmetric Loads on RCS Steam Generator Tube Integrity (Westinghouse)
Yes Yes Steam Generator No Tube Integrity (CE)
Steam Generator No Tube Integrity (B&W)
Mark I Contain.
No Short-Term Prog.
Mark I Contain.
No Long-Term Prog.
Mark II Contain.
No Pool Dynamic Loads Page 1 of 5 c
c NA NA NA NA NA REMARKS SER Supp.4 Sect. 10.4, Amend. 37 PS Ltr.6/9/78 Feedwater Test 7/7/80 original 6/4/81 revised TMI item I.A.2.3, Training Prog.
Accreditation.
Complete 1985 SER Supp.4 Sect. 3.9.1 4/18/80 for Unit 2.
NRC Ltr.
11/24/86 for Unit 1.
PS Ltr. 6/17 /85 PS Ltr.12/16/87
A-9 A-10 A-11 A-12 A-17 A-24 ATWS BWR Feedwater Nozzle Cracking Table 1 Yes No Reactor Vessel Yes Material Toughness Fracture Toughness Yes of Steam Generator and Reactor Coolant Pump Supports Sys. Interactions Yes Qualification of Yes Class IE Safety Related Equip.
Page 2 of 5 c
NA NC c
E c
Unit 1(1EC2173) 7th Outage 10/87-2/88 Unit 2(2EC2174) 4th Outage 8/88-12/88 Human Factors Review (ELE-89-0109)
Comp. 5/3/89 No action req.
unless fracture toughness level predicted < 50 Ft-Lb.
NRC Ltr.1/21/81 SER for Unit 1.
NRC SER Supp.2 Sect. 3.9.4 &
SER Supp. 3 Sect. 3.9.4.
Reviewing with IPE Process IAW GL 88-20.
NRC SER Unit 1 12/5/84 NRC SER Unit 2 1/14/85 PS Ltr. 2/19/85
Table 1 A-26 Reactor Vessel Yes c
NRC SER Supp.3 Pressure Sect. 5.2.3.1 Transient Prot.
installation of Pressurizer overpressure Prot. (POPS)
Unit 2.
Unit 1 POPS installation.
Amend. 24 TS 2/21/80.
A-31 RHR Shutdown Yes c
Unit 2 only.
Requirements NRC SER Supp.3 Sect. 5.7.
Amendment 43 A-36 Control of Yes c
Phase I -
NRC Heavy Loads Acceptance Near Spent 6/22/84 Fuel Phase II -
NRC Closure 6/28/85 A-39 Determination of No NA SRV Pool Dynamic Loads and Pressure Transients*
A-40 Seismic Design Yes E
Evaluating with Criteria IPE Process for External Events A-42 Pipe Cracks in No NA Boiling Water Reactors A-43 Containment Sump Yes c
NRC SER Supp.5 Performance Sect. 6.3.3.7 Unit 2.
No docum. for Unit 1, but similar design.
Page 3 of 5
Table 1 A-44 Station Blackout Yes I
Item 1-10/90 Item 2-Complete Item 3-Complete Item 4-Will be comp. within 2 yrs. of NRR notification IAW 10CFR50.63 (c) (3)
A-45 Shutdown Decay Yes E
Incorporated Heat Removal into IPE effort Requirements A-46 Seismic Qual.
Yes I
PS Ltr. 8/7/89 of Equipment Walkdowns to be in Operating comp. within 2 Plants outages of NRC approval.
Tentative dates Unit 1-1/30/92 Unit 2-6/30/91 Integrated with IPE external events.
A-47 Safety Implication Yes E
Response to GL of Control Systems 89-19 due 3/90.
A-48 Hydrogen Control Yes c
NA for large,
& Effects of dry,PWRs.
Hydrogen Burns on Safety-Related PS Ltr. 1/4/80 NRC SER 3/21/81 Supp.4 4/24/81 Generic Issue 121 tracking.
Page 4 of 5
A-49 Pressurized Thermal Shock Table 1 Yes Page 5 of 5 I
Comp. prelim.
RTpts screening via Reg.Guide
- 1. 99 Rev. 2.
Will not reach till after license exp.
PS Ltr.11/17/88 Periodic reeval to compare with predicted value Submitted LCR 88-14 for PT curves,awaiting approval.
USI NO.
A-1 A-2 A-3 A-4 A-5 A-6 A-7 A-8 A-9 A-10 A-11 A-12 A-17 A-24 A-26 A-31 A-36 A-39 A-40 A-42 A-43 Table 2 STATUS OF UNRESOLVED SAFETY ISSUES FOR HOPE CREEK TITLE APPLICABILITY STATUS Water Hammer Asymmetric Loads on RCS Pressure Transients Generator and RCP Supports Steam Generator Tube Integrity (Westinghouse)
Steam Generator Tube Integrity (CE)
Steam Generator Tube Integrity (B&W)
Mark I Short Term Program Mark I Long Term Program Mark II Pool Dynamic Loads ATWS BWR Feedwater Nozzle Cracking Reactor Vessel Material Toughness Fracture Toughness of Steam Systems Interactions Qualification of lE Equipment Pressure Transient Protection RHR Shutdown Requirements Control of Heavy Loads SRV Pool Dynamic Loads and Seismic Design Criteria Pipe Cracks in BWRs Containment Sump Performance Page 1 of 6 Yes C (7/86)
No NA No No No Yes Yes No Yes Yes Yes No Yes Yes No Yes Yes Yes Yes Yes Yes NA NA NA c (7 /86) c (7/86)
NA c (11/87) c (10/88)
NC NA E
c (7/86)
NA c (7/86) c (7/86) c (7/86)
E I (1990) c (7/86)
USI NO.
A-44 A-45 A-46 A-47 A-48 A-49 Table 2 TITLE Station Blackout Shutdown Decay Heat Removal Seismic Qualification of Equipment in Operating Plants Safety Implication of Control Systems Hydrogen Control Pressurized Thermal Shock
- See discussion under remarks section.
REMARKS USI A-1 Water Hammer APPLICABILITY STATUS Yes I (*)
Yes E
No NA Yes E
Yes c (7/86)
No NA A description of the HCGS design which includes various water hammer mitigation features was provided in the FSAR.
In the HCGS SER (NUREG-1048) and subsequent supplements, the NRC staff found the HCGS design acceptable but never specifically addressed the issue of water hammer.
PSE&G assumes that if the staff had been dissatisfied with the actions taken by the HCGS in dealing with the water hammer issue, this would have been addressed in the SER.
PSE&G therefore considers this issue closed.
Information concerning the water hammer issue was submitted on August 5, 1985 to support a request to eliminate postulation of intermediate pipe breaks.
NRC response an approval of this request are documented in Section 3.6.2 and Appendix O of Supplements 3 and 5 of the HCGS SER.
USI A-2 USI A-3 USI A-4 USI A-5 Asymmetric Loads on RCS steam Generator Tube Integrity (Westinghouse)
Steam Generator Tube Integrity (CE)
Steam Generator Tube Integrity CB&W)
As indicated in Section 1.12 of the HCGS FSAR and Appendix c of the HCGS SER (NUREG-1048), these USis are not applicable to HCGS.
Page 2 of 6
USI A-6 USI A-7 USI A-39 Table 2 Mark I Short Term Program Mark I Long Term Program SRV Pool Dynamic Loads and Pressure Transients HCGS submitted a plant unique analysis report (PUAR) to address these issues.
In Section 6.2.1.7 of the HCGS SER (NUREG-1048),
the staff's preliminary review concluded that the the HCGS analysis was reasonably conservative and in conformance with NUREG-0661; closure was therefore considered confirmatory.
In Section 6.2.1.7 of Supplement 3 of the HCGS SER, the staff concluded that the pool dynamic loads utilized by HCGS were conservative and acceptable.
Appendix N of Supplement 3 included a review of the HCGS PUAR by Brookhaven National Laboratory.
In Section 3.9.3.1 of Supplements 4 and 5 of the HCGS SER, the staff concluded that these issues were fully closed.
Implementation was therefore complete prior to issuance of the HCGS operating license.
USI A-8 Mark II Pool Dynamic Loads As indicated in Section 1.12 of the HCGS FSAR and Appendix c of the HCGS SER (NUREG-1048), this USI is not applicable to HCGS.
USI A-9 ATWS An NRC SER dated October 14, 1987 concluded that HCGS is in compliance with the ATWS rule for the ARI and ATWS/RPT systems.
The SER also concluded that HCGS would be in compliance with the ATWS rule for the SLC system as soon as the proposed Technical Specification changes for the SLC system were approved.
The SLC system Technical Specifications were received as Amendment 11 to the HCGS Operating License on November 9,1987.
Implementation of the ATWS rule were therefore complete for HCGS on November 9, 1987.
USI A-10 BWR Feedwater Nozzle Cracking Information concerning conformance to the requirements of NUREG-0619 for the feedwater nozzles was provided in the response to FSAR Question 210.32.
This information was subsequently incorporated into Section 3.9.5.1.2.3 of the HCGS FSAR in Amendment 6.
The staff found the design of the reactor pressure vessel internals acceptable as documented in Section 3.9.5 of the HCGS SER (NUREG-1048).
Information concerning the control rod hydraulic system was provided in Section 4.6.1.2.4 of the FSAR and found acceptable in Section 4.6 of the HCGS SER.
Results of feedwater nozzle examinations for HCGS were provided in a letter dated October 4, 1988.
Implementation of the requirements of this USI were therefore complete as of October 4, 1988.
Page 3 of 6
Table 2 USI A-11 Reactor Vessel Material Toughness Section 5.3.1.2 of the HCGS SER (NUREG-1048) concluded that all beltline materials have adequate toughness to meet Paragraph IV.A.1 of Appendix G to 10 CFR 50 (Charpy upper-shelf energy no less than 75 ft-lbs initially and maintained above 50 ft-lbs throughout plant life).
No changes or actions were necessary for HCGS since material toughness is postulated to remain above 50 ft-lbs throughout plant life.
USI A-12 Fracture Toughness As indicated in Section 1.12 of the HCGS FSAR and Appendix C of the HCGS SER (NUREG-1048), this USI is not applicable to HCGS.
USI A-17 Systems Interaction This USI is still under evaluation and being reviewed using the IPE process in accordance with Generic Letter 88-20.
USI A-24 Qualification of lE Equipment In Section 3.11 of Supplement 5 to the HCGS SER (NUREG-1048), the staff concluded that the HCGS environmental qualification program is acceptable.
It was further concluded that HCGS had demonstrated conformance with the requirements for environmental qualification as detailed in 10 CFR 50.49, relevant parts of GDC 1 and 4, and Sections II, XI, and XVII of Appendix B to 10 CFR 50, and with the criteria specified in NUREG-0588.
This issue was therefore closed out prior to issuance of the HCGS operating license.
USI A-26 Pressure Transient Protection As indicated in Section 1.12 of the HCGS FSAR and Appendix c of the HCGS SER (NUREG-1048), this USI is not applicable to HCGS.
USI A-31 RHR Shutdown Requirements NRC acceptance of the HCGS RHR system and its conformance to SRP Section 5.4.7 and all applicable regulations is documented in Section 5.4.7 of the HCGS SER (NUREG-1048).
Implementation of this USI was therefore complete prior to issuance of the HCGS operating license.
Page 4 of 6
Table 2 USI A-36 Control of Heayy Loads The HCGS submitted responses to this USI in letters dated June 28, 1983, September 7, 1984, and November 5, 1984.
In Supplement 1 of the HCGS SER (NUREG-1048), the staff concluded that the guidelines of NUREG-0612 Section 5.1.1 had been satisfied.
In addition, the staff concluded that the guidelines of NUREG-0612 had been satisfied for HCGS and no further action was required concerning Sections 5.1.2 through 5.1.5 of NUREG-0612.
Implementation of this USI was therefore complete prior to issuance of the HCGS operating license.
USI A-40 Seismic Design Criteria As indicated in the summary of this USI in Generic Letter 89-21, the resolution of this issue concluded that for plants not covered under the scope of USI A-46, tanks were reviewed to current licensing requirements and found acceptable.
HCGS is one of the plants not covered under the scope of USI A-46.
The revised provisions are being taken into account in the IPE process for external events.
USI A-42 Pipe Cracks in BWRs In an SER dated November 8, 1989, The NRC staff concluded that the HCGS response to Generic Letter 88-01 is acceptable with the exception of the positions concerning leak detection and the piping ISI program.
PSE&G is preparing to address these exceptions and will submit a license change request to resolve these issues in 1990.
USI A-43 Containment Sump Performance In Section 6.2.2 of the HCGS SER (NUREG-1048), the NRC staff concluded that the HCGS response to the concerns of USI A-43 was acceptable.
Implementation of this USI was therefore complete prior to issuance of the HCGS operating license.
USI A-44 Station Blackout PSE&G responded to the resolution of this USI in a letter dated April 17, 1989.
This letter committed to:
(1) complete required revisions to the station blackout procedure by January 1990, (2) complete initial operator training by April 1990, (3) upgrade the simulator if appropriate by October 1990, (4) revise the electrical restoration plan by October 1990, and (5) complete equipment modifications within two years after notification provided in accordance with 10 CFR 50.63.
Page 5 of 6
Table 2 USI A-45 Shutdown Decay Heat Removal This USI is being evaluated in accordance with the IPE process (Generic Letter 88-20).
USI A-46 Seismic Qualification of Equipment As indicated in Section 1.i2 of the HCGS FSAR and Appendix C of the HCGS SER (NUREG-1048), this USI is not applicable to HCGS.
USI A-47 Control Systems This issue is under evaluation with response to Generic Letter 89-19 due in March 1990.
USI A-48 Hydrogen Control The HCGS uses Nitrogen to inert the drywell and has therefore implemented the requirements associated with this USI.
Implementation of this USI was complete prior to issuance of the HCGS operating license.
USI A-49 Pressurized Thermal Shock As indicated in Section 1.12 of the HCGS FSAR and Appendix C of the HCGS SER (NUREG-1048), this USI is not applicable to HCGS.
Page 6 of 6