ML18153C285

Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues

ML18153C285
Person / Time
Site:	Surry, North Anna
Issue date:	07/06/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-291, GL-90-04, GL-90-4, NUDOCS 9007160261
Download: ML18153C285 (8)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 6, 1990 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO NRC GENERIC LETTER 90-04 STATUS OF GENERIC SAFETY ISSUES Serial No. NURPC Docket Nos. License Nos.90-291 50-280 50-281 50-338 50-339 DPR-32 DPR-37 NPF-4 NPF-7 As specified in Generic Letter 90-04, dated April 25, 1990, Virginia Electric and Power Company is providing the implementation status of the generic safety issues listed in Enclosure 1 of the generic letter. The requested information is_ provided in the attachment.

The implementation status as listed in the attachment was derived through a review of correspondence submitted by the Company and NRC's subsequent safety evaluations or letters. Should you have further questions, please contact us. W. . t art Senior ice President

-Nuclear Attachment 9007160261 900706 PDR ADOCK 05000280 P PDC cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. M. S. Lesser NRC Senior Resident Inspector North Anna Power Station FACILITY NAMES: SURRY 1 &2, NORTH ANNA 1 &2 DOCKET NOS.: 50-280, 50-281, 50-338, 50-339 LICENSEE:

VIRGINIA ELECTRIC AND POWER COMPANY STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSl/(MPA NO.) 40 (B065) 41 (B058) 43 (8107) 51 (L913) 67.3.3 (A017) TITLE Safety Concerns Associated With Pipe Breaks In The BWR Scram System BWR Scram Discharge Volume Systems Reliability Of Air Systems Improving The Reliability Of Open-Cycle Service Water Systems Improved Accident Monitoring

• Dates are licensee letters to NRC. # is the serial number. STATUS NA NA COMMENTS*

C** 2/21/89 #88-578 **The GL 88-14 requirements have been met. Compliance with ISA Standard 7.3(particulate standards), as committed to in our GL response has not been attained at SPS. Correspondence noting this difference with the standard is forthcoming.

1 /29/90 #89-572 To be completed by 12/93 C (NAPS) 1 /31 /84 (NAPS) #054 I (SPS) 5/1 0/85 (NAPS) #85-094 -5/10/85 (SPS) #85-123A 6/21/85 (SPS) #85-123AA 7/5/85 (NAPS) #85-094A 8/2/85 (NAPS) #85-094B 8/2/85 (SPS) #85-123B 4/21 /86 (SPS 1) #86-191 8/12/87 (SPS) #87-323 SPS emergency damper position and vital bus voltage indication to be completed next refueling outages.

GSl/(MPA NO.) 75 (8076) 75 (8085) 75 (8077) 75 (8086) 75 (L003) 75 (8078) 75 (8079) 75 (8087) TITLE Item 1.1 -Post-Trip Review (Program Description and Procedure)

Item 1.2 -Post-Trip Review -Data and Information Capability Item 2.1 -Equipment Classification and Vendor Interface (Reactor Trip System Components)

Item 2.2.1 -Equipment Classification for Safety-Related Components Item 2.2.2 -Vendor Interface for Safety-Related Components Items 3.1.1 & 3.1.2 -Post-Maintenance Testing (Reactor Trip System Components)

Item 3.1.3 -Post-Maintenance Changes to Test Requirements (Reactor Trip System Components)

Items 3.2.1 & 3.2.2 -Post-Maintenance Testing (All Other Safety-Related Components) STATUS C C C C C C C COMMENTS 11/4/83 #617 2/8/85 #85-063 11 /4/83 #617 2/8/85 #85-063 11 /4/83 #617 2/8/85 #85-063 5/20/85 (SPS) #85-211 11 /4/83 #617 2/8/85 #85-063 11 /4/83 #617 2/8/85 #85-063 Continuing to evaluate per GL 90-03 11 /4/83 #617 2/8/85 #85-063 10/2/85 (NAPS) #85-494A 10/2/85 (SPS) #85-529A 11 /4/83 #617 2/8/85 #85-063 **l C* 11 /4/83 #617 2/8/85 #85-063 e 10/2/85 (NAPS) #85-494A 1 0/2/85 (SPS) #85-529A *Although the initial commitment is considered complete, additional actions are being taken to resolve concerns identified during recent inspections at SPS.

GSl/(MPA NO.) TITLE STATUS COMMENTS 75 (B088) Item 3.2.3 -Post-Maintenance Testing-C 11 / 4/83 #61 7 Changes to Test Requirements (All 2/8/85 #85-063 Other Safety-Related Components) 75 (B080) Item 4.1 -Reactor Trip System Reliability C 11 /4/83 #617 (Vendor-Related Modifications) 2/8/85 #85-063 75 (B081) Items 4.2.1 & 4.2.2 -Reactor Trip System C 11 /4/83 #617 Reliability

-Maintenance and Testing 2/15/85 #85-063 (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 -Reactor Trip System Reliability

-C 11 /4/83 #617 Design Modifications (Automatic Actuation 2/8/85 #85-063 of Shunt Trip Attachment for Westinghouse 4/1/85 #701 and B&W Plants) 75 (B090) Item 4.3 -Reactor Trip System Reliability

-C 4/12/85 (NAPS) #85-228 Tech Spec Changes (Automatic Actuation 4/12/85 (SPS) #85-229 of Shunt Trip Attachment for Westinghouse 9/9/85 (NAPS) #85-228A and B&W Plants) 9/9/85 (SPS) #85-229A 9/25/86 (SPS) #86-509 10/7/85 (SPS) #85-229B 9/1 /89 (SPS) #89-562 12/28/89 (SPS) #89-562A 75 (B091) Item 4.4 -Reactor Trip System Reliability NA e (Improvements in Maintenance and Test Procedures for B&W Plants)

GSl/(MPA NO.) 75 (8092) 75 (8093) 86 (8084) 93 (8098) 99 (L817) 124 A-13 (8017) TITLE Item 4.5.1 -Reactor Trip System Reliability

-Diverse Trip Features (System Functional Testing) Items 4.5.2 & 4.5.3 -Reactor Trip System Reliability

-Test Alternatives and Intervals (System Functional Testing) Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Auxiliary Feedwater System Reliability Snubber Operability Assurance

-Hydraulic Snubbers STATUS C C NA C COMMENTS 11 /4/83 #617 2/8/85 #85-063 12/27/85 (NAPS 1) #85-49Ll-C 11 /4/83 #617 2/8/85 #85-063 5/20/85 (SPS) #85-211 8/29/85 (SPS) #85-211 B 10/31/85 (SPS) #85-211 C 11 /18/85 (NAPS) #85-695 9/25/86 (SPS) #86-509 1/30/87 (NAPS) #86-655 e 5/23/88 #88-101 9/23/87 #87-453 1 /6/89 #88-737 2/3/89 #88-737 A 9/29/89 (SPS) #88-7378 1 0/31 /89 #88-737C Hardware modifications for both stations will be completed during the upcoming refueling outages. In addition, review of WOG perturbation studies will be completed per e GL 88-17 actions. 4/27/90 (NAPS) #90-183 Pending NRC approval for NAPS Tech Specs. NA C 9/19/85 (NAPS) #85-645 9/24/85 (NAPS) #85-686 12/20/85 (SPS) #85-751A GSl/(MPA NO,) A-13 (B022) A-16 (0012) A-35 (B023) 8-10 TITLE Snubber Operability Assurance

-Mechanical Snubbers Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems Behavior of BWR Mark Ill Containments STATUS C NA COMMENTS 9/19/85 (NAPS) #85-645 9/24/85 (NAPS) #85-686 12/20/85 (SPS) #85-751 A C (SPS) 7/5/79 (NAPS 1) C* (NAPS) #352/050279

.* 1 0/9ll9 #673/080879 11 /28/79 (NAPS) #673A/080879

-8/20/80 (NAPS 1) #725 9/24/80 (NAPS 1) #725A 10/22/80 (NAPS 1) #725 5/26/81 (SPS) #233 7/24/81 (NAPS) #908A 8/21/81 (NAPS) #908A 9/23/81 (NAPS) #908B 12/1/81 (NAPS) #908B 12/31/81 (SPS) #233A 1 /20/82 (NAPS) #017 2/26/82 (NAPS) #076 3/31/82 (SPS) #175 6/11/82 (SPS) #317 11 /12/82 (SPS) #638 12/23/85 (NAPS 1) #85-750Be 1/29/86 (NAPS) #85-261 5/2/86 (NAPS 2) #86-198 2/24/87 (SPS) #86-736 *NAPS 2 generator breaker to be installed in 1992. NRC approval pending for load shed removal. (See 1 /29/86 letter.) NA

' . GSI/(MPA NO.) TITLE STATUS COMMENTS . ' 8-36 Develop Design, Testing and Maintenance NA "' Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems 8-63 (8045) Isolation of Low Pressure Systems Connected to C 3/1 4/80 #154/022580 the Reactor Coolant System Pressure Boundary