ML13322B057
| ML13322B057 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/30/1989 |
| From: | Nandy F SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8912050229 | |
| Download: ML13322B057 (5) | |
Text
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Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 F. R. NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING (714) 587-5400 November 30, 1989 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Status of Implementation of Unresolved Safety Issue Requirements San Onofre Nuclear Generating Station Unit 1 This letter provides the status on implementing Unresolved Safety Issue (USI) requirements at San Onofre Unit 1 (SONGS 1).
The letter is in response to Generic Letter 89-21, "Request for Information Concerning Status of Implementation of Unresolved Safety Issue Requirements," dated October 19, 1989.
The USI implementation status for SONGS 1 is summarized in the enclosure to this letter for all USI's for which the NRC has issued final technical resolution.. The enclosure is formatted to provide the information required in to the Generic Letter.
If you have any questions, please contact me.
Very truly yours, cc: J. B. Martin, Regional Administrator, NRC Region V C. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 8912050229 891130 -
0 PDR ADOCK 05000206 P
ENCLOSURE STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 USI/MPA Number Title Ref. Documents Applicability Status/Date*
Remarks A-1 Water Hammer SECY 84-119 All C - 11/25/80 NRC SER dated 4/22/80 with additional NUREG-0927, Rev. 1 information submitted by SCE letter dated NUREG-0993, Rev. 1 11/25/80. Modification to Auxiliary Feed NUREG-0737, Item water System completed during Cycle 10 I.A.2.3 refueling outage incorporated design features SRP revisions to prevent water hammer. NRC SER issued April 25, 1989.
NUREG-1190 (undated, received by SCE on 1/22/86) attributed 11/21/85 water hammer event primarily to check valve failures.
A-2/
Asymmetric Blowdown NUREG-0609 PWR C - 7/25/89 Letter, C. M. Trammell to K. P. Baskin, MPA D-10 Loads on Reactor GL 84-04, GDC-4 "Elimination of Postulated Breaks in Primary Cooling Systems Primary Coolant Piping," 7/25/89.
A-3 Westinghouse Steam NUREG-0844 W-PWR C - 6/26/85 SCE to NRC letter, "Steam Generator Tube Generator Tube SECY 86-97 Integrity Program," 6/26/85.
Integrity SECY 88-272 GL 85-02 (No requirements)
A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR N/A Integrity SECY 88-272 GL 85-02 (No requirements)
A-5 B&W Steam Generator NUREG-0844, SECY 86-97 B&W-PWR N/A Tube Integrity SECY 88-272 GL 85-02 (No requirements)
A-6 Mark I Containment NUREG-0408 Mark I-BWR N/A Short-Term Program A-7/D-01 Mark I Long-Term NUREG-0661 Mark I-BWR N/A Program NUREG-0661, Suppl. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR N/A Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SRP 6.2.1.1C GDC 16
- C - COMPLETE N/C - NO CHANGES NECESSARY N/A - NOT APPLICABLE TO SONGS 1 I -
INCOMPLETE E - EVALUATING ACTIONS REQUIRED STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 USI/MPA Number Title Ref. Documents Applicability Status/Date*
Remarks A-9 Anticipated Transients NUREG-0460, Vol. 4 All I - 12/2/90 Final design and implementation of Without Scram 10 CFR 50.62 estimated diverse turbine trip remain per SCE letter, "FTOL Open Items,' 10/2/89.
A-10/
BWR Feedwater Nozzle NUREG-0619 BWR N/A MPA B-25 Cracking Letter from DG Eisenhut dated 11/18/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All N/C No licensee response required per GL 82-26.
Toughness 10 CFR 50.60 Acceptibility of SONGS 1 reactor vessel GL 82-26 documented by the NRC in NUREG-0081 and NUREG-0569.
A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWR N/A No further licensee action required.
Steam Generator and SRP Revision As documented in NUREG-Osil, Rev.l, NRC Reactor Coolant Pump 5.3.4 action was to issue new SRP which is Supports applicable only to PWRs with construction permit issued after October, 1983.
A-17 Systems Interactions Ltr:
DeYoung to All N/C No licensee actions required per GL 89-18.
licensees - 9/72 NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/
CR-1261, NUREG/CR-4470, GL 89-18 (No requirements)
A-24/
Qualification of Class NUREG-0588, Rev. 1 All C 3/11/85 NRC SER issued 3/11/85.
MPA B-60 1E Safety-Related Equipment SRP 3.11 10 CFR 50.49 GL 82-09, GL 84-24 GL 85-15 A-26/
Reactor Vessel Pressure DOR Letters to PWR C
12/16/88 Overpressurization mitigating system (OMS)
MPA B-04 Transient Protection Licensees 8/76 per 10/12/77 SCE letter installed during NUREG-0224 Fall 1978 refueling outage. An Amendment NUREG-0371 Application with revised Technical SRP 5.2 Specification OMS requirements to be GL 88-11 submitted by 1/31/90 per SCE letter dated 11/6/89. Technical Specification pressure temperature limits were reviewed and found acceptable per GL 88-11 requirements via 12/16/88 SCE letter.
S iC
- COMPLETE N/C - NO CHANGES NECESSARY N/A - NOT APPLICABLE TO SONGS 1 I -
INCOMPLETE E - EVALUATING ACTIONS REQUIRED STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 USI/MPA Number Title Ref. Documents Applicability Status/Date*
Remarks A-31 Residual Heat Removal NUREG-0606 All OLs After N/A SONGS 1 is a Class 3 plant per SRP 5.4.7, RG 1.113 1/79 Branch Technical Position RSB 5-1, RG 1.139 that was licensed prior to 1/79.
SRP 5.4.7 A-36/
Control of Heavy Loads NUREG-0612 All I - 2/9/93 Phase II modification implementation C-10, Near Spent Fuel SRP 9.1.5 estimated remains per 10/2/89 SCE letter.
C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR N/A Pool Dynamic Loads NUREGs-0763, 0783, 0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design Criteria SRP Revisions, NUREG/
All N/C SONGS 1 seismic evaluation included in SEP CR-4776, NUREG/CR-0054, and USI No. A-46 (Ref. NUREG-1233).
NRC NUREG/CR-3480, NUREG/
issued SER on SONGS 1 Long-Term Service CR-1582, NUREG/CR-1161, Seismic Re-evaluation Program on 7/11/86.
NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev. 1 BWR N/A MPA B-05 Water Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All N/C No licensee action required. NRC revised Sump Performance NUREG-0869, Rev. 1 RG 1.82, Rev. 0 and SRP 6.2.2 per NUREG-0897, NUREG-0897, RG 1.82 Rev. 1.
(Rev. 0), SRP 6.2.2 GL 85-22 (No requirements)
A-44 Station Blackout RG 1.155 All I - 1/1/92 Approval of plan by NRC and implementation of NUREG-1032 estimated procedures remain per 10 CFR 50.63 and 4/17/89 NUREG-1109 SCE letter.
- C - COMPLETE N/C - NO CHANGES NECESSARY N/A - NOT APPLICABLE TO SONGS 1 I -
INCOMPLETE E - EVALUATING ACTIONS REQUIRED STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 USI/MPA Number Title Ref. Documents Applicability Status/Date*
Remarks A-45 Shutdown Decay Heat SECY 88-260 All I - 9/1/92 To be handled via Individual Plant Examination Removal Requirements NUREG-1289 estimated (IPE) Program per SECY 88-260. (SCE letter NUREG/CR-5230 11/3/89, "IPE for Severe Accident Vulnera SECY 88-260 bilities, SONGS 1, 2 and 3.")
(No requirements)
A-46 Seismic Qualification NUREG-1030 All I - 11/92 Perform plant walkdown by 11/92 per 10/2/89 of Equipment in NUREG-1211 estimated and 10/7/88 SCE letters.
SQUG Generic Operating Plants GL 87-02, GL 87-03 Implementation Procedure not yet issued.
A-47 Safety Implication NUREG-1217, NUREG-1218 All E - 1/93 Implement Steam Generator Overfill Protection, of Control Systems GL 89-19 estimated if necessary, by 1/93 per 10/2/89 SCE letter.
Status letter due 3/20/90 per GL 89-19.
A-48 Hydrogen Control 10 CFR 50.44 All, except C - 11/2/82 Completed with SCE installation of hydrogen Measures and Effects SECY 89-122 PWRs with recombiners as part of TMI Action Plan Item of Hydrogen Burns on large dry No. II.E.4.1, per 11/2/82 NRC letter.
Safety Equipment containments A-49 Pressurized Thermal RGs 1.154, 1.99 PWR C - 1/23/86 Completed per 1/23/86 SCE letter. As Shock SECY 82-465 documented in 12/16/88 SCE letter, no changes SECY 83-288 required as a result of GL 88-11.
SECY 81-687 10 CFR 50.61 GL 88-11 LNRC.SN
- C -
COMPLETE N/C - NO CHANGES NECESSARY N/A - NOT APPLICABLE TO SONGS 1 I -
INCOMPLETE E - EVALUATING ACTIONS REQUIRED