ML20055D322
| ML20055D322 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/28/1990 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.097, TASK-***, TASK-OR GL-88-14, GL-89-13, GL-90-03, GL-90-04, NUDOCS 9007060178 | |
| Download: ML20055D322 (7) | |
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GPU Nuo6ser Corporetten
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Post Office Box 388
,4 Route 9 South Forked River New Jersey 087310368 609S'1 4000 Wnten
'ect Dial Number; June 28,1990 U.S. Nuclear Regulatory commission Attne Document Control Desk Washington, D.C.
20555 Dear sir Subjects Oyster Creek Nuclear Generating Station Docket No. 50-219 Response to Generic Letter 90-04 Status of Licensee Irnplementation of Generic Safety Issues Resolved with Imposition of Requirement 9 or Corrective Actions As requested by Generic Letter 90-04 dated April 25, 1990, this response provides the status of all generic safety issues which arply to the Oyster Creek Huclear Generating facility.
If further information is required, please contact Brenda DeMerchant, OC Licensing Engineer at (609) 971-4642.
Very truly yours,
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E.E. Fitzp trick Vice President and Director Oyster Creek
-EEF/BDeM/je Enclosure cci Mr. Thomas Martin, Administrator Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 j
NRC Resident Inspector
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I Oyster Creek Nuclear Generating Station Mr. Alexander Dromerick U.S. Nuclear Regulatory Commission Mail Stop No. P1-137 Washington, DC 20555 fCK0500021;,
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GPU Nuclear Corporauvo is a subsidiary of General Public Utilities Corporation l
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FACILITY NAME2 Oyster Creek Dor 1tET NO:
50-219 LICENSEES CPU Nuclear Corporation and Jersey Central Power and Licht STATUS OF LTCENSE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS GSI/fMPA Wo.)
TITLE APPLICABILITY STATUS COMMENTS 40 (8065)
Safety concerns Associated With All BWRs C
1/86 Pipe Breaks in the BWR Scram System 41 (8058)
BWR Scram Discharge Volume Systems All BWRs C
1983 43 (BIO 7)
Reliability of Air Systems All Plants See Note (1) 51 (L913)
Improving the Reliability of All Plants I
See Note (2)
Open-cycle Service Water Systems 67.3.3 (A017)
Improved Accident Monitoring All Plants I
See Note (3) 75 (3076)
Item 1.1 - Post Trip Review All Planta C
NRC SER dated 5/85 (Program Description & Procedure) 75 (BO85)
Item 1.2 - Post Trip Review All Plants C
NRC SER dated 4/86 Data and Information Capability O
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- GSI/fMPA No.1 TITLE
- APPLICABItI R STATUS COMMENTS 75 (8077)
Item 2.1 - Equipment Classification All Plants-C 10/85 and Vendor Interface (Reactor Trip
~ System v - ts) 75 (8086)
~ Item 2.2.1 - Equipment Classification All Planta C
NRC SER dated 10/88 for Safety-Related v - ts 75 (LOO 3)
Item 2.2.2 - Vendor Interface for All Plants E
See Note (4)
Safety-Related Components 75 (8078)
Items 3.1.1 & 3.1.2 - Post-Maintenance All Planta C
NRC SER dated 3/4/88 Testing (Reactor Trip System P ats) 75 (8079)
Item 3.1.3 - M t-Maintenance Testing All Plants C
10/85 Changes to Test Requi-ements (Reactor Trip System Components) 75 (8087)
Items 3.2.1 & 3.2.2 - Poet Maintenance All Planta C
NRC SER dated 3/4/88 Testing (All Other Safety Related components) 75 (B088)
Item 3.2.3 - Post-Maintenance Testing All Plants C
10/85 Chanc;ps to Test Requirements (All Other Safety-Related Components) 75 (BO80)
Item 4.1 - Reactor Trip System All Placts N/A Reliability (vendor-Related Modifications)
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_3-GSI/fMPA No.1 TITLE APPLICABILITY STATUS COMMEhTS
- 75 (3081)
Items 4.2.1 & 4.2.2 - Reactor Trip.
All FWRs N/A System Relisbility Maintenance and Testing (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (8032)
Item 4.3 - Reactor Trip System All W and B&W N/A Reliability - Design Modifications Plants (Actomatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (3090)
Item 4.3 - Reactor Trip System All W & B&W N/A Reliability - Tech spec changes Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B091)
Item 4.4 - Reactor Trip System All B&W Plante N/A Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
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3 CST /fMFA No.1 TITLE APPLICABILITY STATUS CODENTS
' 75 (2092)
Item 4.5.1 - Reactor Trip System All Planta C
NRC SER dated 3/4/88 Reliability - Civerse Trip Featares (3ystesa Functional Testing) 75 (3093)
Items 4.5.2 & 4.5.3 - Reactor Trip All Planta C
6/85 System Keliability - Test Alter-natives and Intervels (System Functional Testing) 86 (8084)
Long Range Plan for Dealing with All BWRs C
See Note (5) stress Corrosion Cracking in BWR Piping 93 (8098)
Steam Binding of Auxiliary Feedwater All FWRs N/A W
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99 (LS17)
RCS/RER Suction Line Valve All PWRs N/A Interlock on PWRs 124 72xiliary Feedwater System ANo-le2, Rancho N/A peliability Seco, Prairie Island 1&2, Crystal River-3, Ft. Calhoun A-13 (BOl73 Snubber Operability Assurance -
All Plants C
4/86 Eydraulic snubbers
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_ CSI/fMPA No.1 TITLE
&EPLICABILITY STATUS COMMENTS A-13 (8022)
Snubber Operability Assurance All Plants C
4/86 A-16 (D012)
Steam Effects on BWR Core Oyster Creek C
Spray Distribution
& NMP-1 A-35 (8023)
Adequacy of Offsite Power All Planta C
2/85 Systems i
B-lO Behavior of BWR Mark III All BWR Mark III N/A Containments Planta B-36 Develop Design, Testing, and All Plants with OL N/A Maintenance Criteria for Atroosphere Applications After Cleanup System Air Filtration 4/1/80 and Adsorption Units for Engineered Safety Features Systees and for Normal ventilation Systess a-63 (8045)
Isolation of I,ow Pressure Systems All Planta C
8/81 Connected to the Reactor Coolant System Pressure Soundary me..
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See GPUN response to GL 88-14 dated 2/21/89.
(2)
GPUN letter dated January 30, 1990 provided responses to each of the NRC's recommended actions resulting from CL 89-13.
Several evaluations are currently ongoing and future correspondence with the NRC related to GL 89-13 is expected.
i (3)
By GPUN letter dated 4/13/90 a revised copy of Topical Report 028 (Rev. 1) was submitted for NRC review. GPUN is currently awaiting an NRC SER concerning OCNGS Reg. Guide 1.97 compliance.
GPUN plans to submit a resolution to several deficir;.cies noted during our evaluation of Reg. Guide 1.97 comp 41ance by the end of the third quarter of 1990.
l (4)
Response due to NRC within 180 days of receipt of Oeneric Letter 90-03 h
dated 3/20/90.
I (5)
GPUN to NRC' letter dated 6/7/90 stated a revised inspection plan for 13R will be submitted by August 1990.
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