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 Serial No.90-291 Attention: Document Control Desk NURPC Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 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 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 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.) TITLE STATUS COMMENTS*

40 (B065) Safety Concerns Associated With NA Pipe Breaks In The BWR Scram System 41 (B058) BWR Scram Discharge Volume Systems NA 43 (8107) Reliability Of Air Systems 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.

51 (L913) Improving The Reliability Of Open-Cycle 1/29/90 #89-572 Service Water Systems To be completed by 12/93 67.3.3 (A017) Improved Accident Monitoring 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 semi-vital bus voltage indication to be completed next refueling outages.

• Dates are licensee letters to NRC. # is the serial number.

GSl/(MPA NO.)

75 (8076)

TITLE Item 1.1 - Post-Trip Review (Program STATUS C

COMMENTS 11/4/83 #617

• • l Description and Procedure) 2/8/85 #85-063 75 (8085) Item 1.2 - Post-Trip Review - Data C 11 /4/83 #617 and Information Capability 2/8/85 #85-063 75 (8077) Item 2.1 - Equipment Classification C 11 /4/83 #617 and Vendor Interface (Reactor Trip 2/8/85 #85-063 System Components) 5/20/85 (SPS) #85-211 75 (8086) Item 2.2.1 - Equipment Classification C 11 /4/83 #617 for Safety-Related Components 2/8/85 #85-063 75 (L003) Item 2.2.2 - Vendor Interface for C 11 /4/83 #617 Safety-Related Components 2/8/85 #85-063 Continuing to evaluate per GL 90-03 75 (8078) Items 3.1.1 & 3.1.2 - Post-Maintenance C 11 /4/83 #617 Testing (Reactor Trip System Components) 2/8/85 #85-063 10/2/85 (NAPS) #85-494A 10/2/85 (SPS) #85-529A 75 (8079) Item 3.1.3 - Post-Maintenance Testing- C 11 /4/83 #617 Changes to Test Requirements (Reactor 2/8/85 #85-063 Trip System Components) 75 (8087) Items 3.2.1 & 3.2.2 - Post-Maintenance C* 11 /4/83 #617 e Testing (All Other Safety-Related Components) 2/8/85 #85-063 10/2/85 (NAPS) #85-494A 10/2/85 (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.) TITLE STATUS COMMENTS 75 (8092) Item 4.5.1 - Reactor Trip System Reliability - C 11 /4/83 #617 Diverse Trip Features (System Functional 2/8/85 #85-063 Testing) 12/27/85 (NAPS 1) #85-49Ll-C 75 (8093) Items 4.5.2 & 4.5.3 - Reactor Trip System C 11 /4/83 #617 Reliability - Test Alternatives and Intervals 2/8/85 #85-063 (System Functional Testing) 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 86 (8084) Long Range Plan for Dealing with Stress NA Corrosion Cracking in BWR Piping 93 (8098) Steam Binding of Auxiliary Feedwater Pumps C 5/23/88 #88-101 99 (L817) RCS/RHR Suction Line Valve Interlock on PWRs 9/23/87 #87-453 1/6/89 #88-737 2/3/89 #88-737A 9/29/89 (SPS) #88-7378 10/31 /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 GL 88-17 actions.

e 4/27/90 (NAPS) #90-183 Pending NRC approval for NAPS Tech Specs.

124 Auxiliary Feedwater System Reliability NA A-13 (8017) Snubber Operability Assurance - Hydraulic C 9/19/85 (NAPS) #85-645 Snubbers 9/24/85 (NAPS) #85-686 12/20/85 (SPS) #85-751A GSl/(MPA NO,) TITLE STATUS COMMENTS A-13 (B022) Snubber Operability Assurance - Mechanical C 9/19/85 (NAPS) #85-645 Snubbers 9/24/85 (NAPS) #85-686 12/20/85 (SPS) #85-751 A A-16 (0012) Steam Effects on BWR Core Spray NA Distribution A-35 (B023) Adequacy of Offsite Power Systems C (SPS) 7/5/79 (NAPS 1)

C* (NAPS) #352/050279 10/9ll9 #673/080879 11 /28/79 (NAPS)

1. 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.)

8-10 Behavior of BWR Mark Ill Containments 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