ML13322B174
| ML13322B174 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/27/1990 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9006290027 | |
| Download: ML13322B174 (5) | |
Text
Southem California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 June 27, 1990 R.M.ROSENBLUM TELEPHONE MANAGER OF (714) 587-5420 NUCLEAR REGULATORY AFFAIRS U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Status of Implementation of Generic Safety Issue Requirements San Onofre Nuclear Generating Station Unit 1 This letter provides the status of implementing Generic Safety Issue (GSI) requirements at San Onofre Nuclear Generating Station, Unit 1 (SONGS 1).
The letter is in response to Generic Letter 90-04, "Request for Information on the Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions," dated April 25, 1990.
The GSI implementation status for SONGS 1 is summarized in the enclosure to this letter for all GSI'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 900629P0027 900627 PDR ADOCK 05000206 F'DC
ENCLOSURE FACILITY NAME:
San Onofre Nuclear Generating Station, Unit 1 DOCKET NO.:
50-206 LICENSEE:
Southern California Edison STATUS OF SONGS 1 IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS IN RESPONSE TO GENERIC LETTER 90-04 GSI/(MPA No.)
TITLE APPLICABILITY STATUS*
COMMENTS 40 (BO65)
Safety Concerns Associated With Pipe All BWRs NA Breaks In the BWR Scram System 41 (8058)
BWR Scram Discharge Volume Systems All BWRs NA 43 (8107)
Reliability of Air Systems All Plants I 9/30/90 SCE response to GL 88-14 projected for (Estimated)
September 30, 1990.
51 (L913)
Improving the Reliability of Open-Cycle All Plants I 1/15/91 SCE responded to I.E. Bulletin 81-03 by Service Water Systems (Estimated) letters dated June 4, 1981 and August 12, 1982.
Follow-on SCE response to GL 89-13 that was issued on January 26, 1990 committed to notify NRC of completing GL Recommended Actions within 30 days of implementation (during Cycle 11).
67.3.3 (A017)
Improved Accident Monitoring All Plants I 2/93 By letter dated May 2, 1990, SCE committed (Estimated) to complete evaluation of separation of cables/power supplies by June 30, 1991.
By letter dated October 2, 1989, SCE committed to implement any necessary plant modifications by the end of the Cycle 12 refueling outage.
75 (8076)
Item 1.1 - Post-Trip Review (Program All Plants C
NRC SER issued on May 9, 1985.
Description and Procedure) 75 (8085)
Item 1.2 - Post-Trip Review - Data and All Plants I 7/13/90 Additional NRC questions received by Information Capability letter dated May 16, 1990.
75 (8077)
Item 2.1 - Equipment Classification and All Plants I
SCE response submitted November 28, 1983.
Vendor Interface (Reactor Trip System By letter dated March 11, 1985, the NRC Components) indicated they had reviewed the SCE response for completeness and adequacy.
No outstanding SCE action.
75 (8086)
Item 2.2.1 - Equipment Classification for All Plants C
NRC SER issued on April 25, 1988.
Safety-Related Components
- NA - Not Applicable to SONGS 1 NC - No Changes Necessary C - Complete I -
Incomplete E - Evaluating Actions Required STATUS OF SONGS 1 IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS IN RESPONSE TO GENERIC LETTER 90-04 GSI/(MPA No.)
TITLE APPLICABILITY STATUS*
COMMENTS 75 (LO03)
Item 2.2.2 - Vendor Interface for Safety-All Plants I 9/23/90 SCE response to GL 90-03, "Relaxation of Related Components Staff Position on Generic Letter 83-28, Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,'" is scheduled to be issued by September 23, 1990.
75 (8078)
Items 3.1.1 and 3.1.2 - Post-Maintenance All Plants C
NRC SER issued on November 4, 1985.
Testing (Reactor Trip System Components) 75 (8079)
Item 3.1.3 - Post-Maintenance Testing-All Plants C
NRC SER issued on August 19, 1985.
Changes to Test Requirements (Reactor Trip System Components) 75 (B087)
Items 3.2.1 and 3.2.2 - Post-Maintenance All Plants I
Additional information provided to NRC by Testing (All Other Safety-Related letter dated July 24, 1985. No Components) outstanding SCE actions.
75 (B088)
Item 3.2.3 - Post-Maintenance Testing-All Plants C
NRC SER issued on August 19, 1985.
Changes to Test Requirements (All Other Safety-Related Components) 75 (8080)
Item 4.1 - Reactor Trip System All Plants C
NRC SER issued on July 1, 1985.
Reliability (Vendor-Related Modifications) 75 (8081)
Items 4.2.1 and 4.2.2 - Reactor Trip All PWRs C
NRC SER issued on September 16, 1988.
System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (8082)
Item 4.3 - Reactor Trip System All W and B&W C
NRC SER issued on November 28, 1984.
Reliability - Design Modifications Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090)
Item 4.3 - Reactor Trip System All W and B&W C
NRC SER issued on November 28, 1984.
Reliability - Tech Spec Changes Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
- NA - Not Applicable to SONGS 1 NC - No Changes Necessary C - Complete I -
Incomplete E - Evaluating Actions Required STATUS OF SONGS 1 IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS IN RESPONSE TO GENERIC LETTER 90-04 GSI/(MPA No.)
TITLE APPLICABILITY STATUS*
COMMENTS 75 (B091)
Item 4.4 - Reactor Trip System All B&W Plants NA Reliability (Improvements in Maintenance and Test procedures for B&W Plants) 75 (8092)
Item 4.5.1 - Reactor Trip System All Plants C
Deferred to evaluation of Item 4.5.2 per Reliability-Diverse Trip Features (System NRC letter dated November 4, 1985.
Functional Testing) 75 (B093)
Items 4.5.2 and 4.5.3 - Reactor Trip All Plants C (Item 4.5.2)
Justification for not performing on-line System Reliability - Test Alternatives testing of Reactor Trip Breakers provided and Intervals (System Functional Testing) by SCE letters dated June 3, 1987 and November 13, 1987.
NRC concurred that on-line testing is not required in SER issued on September 16, 1988.
C (Item 4.5.3)
NRC SER issued on June 16, 1989.
86 (B084)
Long Range Plan for Dealing with Stress All BWRs NA Corrosion Cracking in BWR Piping 93 (B098)
Steam Binding of Auxiliary Feedwater All PWRs C
SCE responded to I.E. Bulletin 85-01 by Pumps letter dated January 29, 1985 and to GL 88-03 on May 3, 1988.
NRC SER issued on May 11, 1988.
99 (L817)
RCS/RHR Suction Line Valve Interlock on All PWRs I 12/2/90 SCE responded to GL 87-12 by letters dated PWRs (Estimated)
September 24, 1987; December 23, 1987; and February 12, 1988. SCE responded to GL 88-17 by letters dated January 5, 1989; February 1, 1989; and March 27, 1990. The NRC's responses concerning GL 88-17 are contained in letters dated July 12, 1989, April 26, 1990 and June 5, 1990.
Implementation of plant enhancements to be completed by the end of the Cycle 11 refueling outage.
124 Auxiliary Feedwater System Reliability ANO-1&2, Rancho NA Seco, Prairie Island 1&2, Crystal River-3, Ft. Calhoun
- NA - Not Applicable to SONGS 1 NC - No Changes Necessary C - Complete I -
Incomplete E - Evaluating Actions Required STATUS OF SONGS 1 IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS IN RESPONSE TO GENERIC LETTER 90-04 GSI/(MPA No.)
TITLE APPLICABILITY STATUS*
COMMENTS A-13 (Bo17)
Snubber Operability Assurance - Hydraulic All Plants I 9/30/90 NRC SER issued on October 15, 1984.
Snubbers (Estimated)
Exemption of large snubbers (capacity
>120,000 pounds) from testing needs to be removed from Technical Specifications.
A-13 (B022)
Snubber Operability Assurance -
All Plants C
NRC SER issued on October 15, 1984.
Mechanical Snubbers A-16 (0012)
Steam Effects on BWR Core Spray Oyster Creek and NA Distribution NMP-1 A-35 (B023)
Adequacy of Offsite Power Systems All Plants I 2/93 By SCE letter dated October 2, 1989, (Estimated) implementation of modifications that address the potential for degraded grid voltage and the adequacy of SONGS 1 voltage distribution are scheduled for the Cycle 12 refueling outage. NRC concurred with this schedule by Order dated January 2, 1990.
B-10 Behavior of BWR Mark III Containments All BWR Mark III NA Plants B-36 Develop Design, Testing, and Maintenance All Plants with NA Criteria for Atmosphere Cleanup System OL Applications Air Filtration and Adsorption Units for After 4/1/80 Engineered Safety Features Systems and for Normal Ventilation Systems B-63 (B045)
Isolation of Low Pressure Systems All Plants C
Resolved as SEP Topic V-11.A in Connected to the Reactor Coolant System
'Integrated Plant Safety Assessment, Pressure Boundary Systematic Evaluation Program, San Onofre Nuclear Generating Station, Unit 1,"
NUREG-0829, December, 1986.
SO1STAT.SN2
- NA - Not Applicable to SONGS 1 NC - No Changes Necessary C - Complete I -
Incomplete E - Evaluating Actions Required