IR 05000280/1988024
| ML18152B080 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 07/26/1988 |
| From: | Conlon T, Paulk C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152B079 | List: |
| References | |
| 50-280-88-24, 50-281-88-24, 50-338-88-20, 50-339-88-20, GL-83-28, NUDOCS 8808170216 | |
| Download: ML18152B080 (11) | |
Text
-
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., ATLANTA, GEORGIA 30323 Report Nos.:
50-338/88-20 and 50-339/88-20 50-280/88-24 and 50-281/88-24 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-338 and 50-339 50-280 and 50-281 License Nos.:
NPF-4 and NPF-7 DPR-32 and DPR-37 Facility Names:
North Anna Power Station Units 1 and 2 Surry Power Station Units 1 and 2 Inspection Conducted:
June 20-24, 1988 Inspector: C-~
C. Pa Contributing Personnel:
L. Foster, Consultant Approved by:
~
~
¥,pl'-<
T. Confon, cine Plant Systems Section Engineering Branch Division of Reactor Safety SUMMARY Date Signed
~<<.P'V Zateigned Scope:
This special, announced inspection was conducted in the area of previously identified findings in the area of environmental qualification of electrical equipment important to safet Additionally, an in-office review of previously identified items related to Generic Letter 83-28 was performe Results:
In the area inspected, no violations or deviations were identifie The licensee has taken steps well above the minimum required in order to maintain their EQ program above averag The engineering staff at the General Office that is responsible for the overview of Vfi*ginia Power's EQ program is very knowledgeable and very diligent in their efforts to maintain their level of excellenc ~~0 PDR ADOCK O PNU G
- Persons Contacted Licensee Employees REPORT DETAILS R. Calder, Manager, Nuclear Engineering
- P. Conner, Senior Staff Engineer
- R. Cross, Nuclear Specialist, SPS v
M. Duda, Staff Engineer - I&C, SEQ, SPS M. Haduck, Supervisor of Electrical Maintenance, SPS B. Jacobs, Supervisor of Training, NAPS
- P. Knutsen, Supervisor, Nuclear Engineering R. Krick, Senior Staff Engineer, Nuclear Licensing H. Le, Station EQ Coordinator, NAPS S. Murphy, Senior Construction Specialist - Electrical, NAPS
- W. Murray, Senior Engineer, Nuclear Engineering D. Padula, Senior Engineer, Site EQ Coordinator, SPS
- M. Pinion, Senior Staff Engineer D. Roth,*Nµclear Specialist, NAPS
- E. Shaub, Licensing Engineer R. Sprouse, Mechanical Construction Supervisor, NAPS
- H. Sutton, Nuclear Specialist
- R. Woodall, III, System Engineer Other 1 icensee employees contacted during this inspection included craftsmen, engineers, and technician NRC Resident Inspectors L. King, Resident Inspector, NAPS L. Nicholson, Resident Inspector, SPS
- Attended exit interview
__ --=-i,-
Acronyms and initialisms used throughout this report are listed in Paragraph.
Action -oh Previous Inspection Findings (92701}
The licensee responded to NOVs issued to its Surry and North Anna Power Stations on May 23,.and May 19, 1988, respectivel Discussions of each item identified in the NOVs as well as other open items follo (Closed} VIO 280,281/86-12-02, Main Steam Valve House Components Unqualified for Main Steam Line Break (IEN 84-90}
A previous inspection identified that the main steam line pressure transmitters located in the MSVHs at SPS were not qualified for an MSLB,with superheated stea By June 24, 1986, all affected
transmitters had been relocated and modifications had been made in the MSVHs to 1 imit the steam communication between the affected space The inspector reviewed the Environmental Zone Description for the SPS MSVH.s to verify that the zone was not subject to an HELB that would resu*H in a superheated steam environmen The inspector al so verified the location of the transmitters during a plant walkdow The modifications to limit steam communications were also observe Based on the above, this item is considered close (Closed) VIO 280,281/86-12-03, High Head Safety Injection Pump Motor Lube Oil A previous inspection identified that the HHS! Pump motor lube oil was not being replaced at the specified interval as required by the QDR maintenance sectio The licensee installed pump run timers for the affected pumps and revised the QDR maintenance section. The inspector verified that oil sampling was being performed and that the interval did not exceed the 3000 hours0.0347 days <br />0.833 hours <br />0.00496 weeks <br />0.00114 months <br /> (1?5 days) specified in the revised QD In one case the oil was sampled within the time frame, however, the sample was unsatisfactory due to bearing material in the oi By the time the sample results were received and the oil replaced, the pump had run approximately 146 day A JCO was written to show that the pumps were still qualified and the licensee was to revise to QDR to clarify the sample/replacement criteri The licensee has written the following procedures to ensure the sampling/replacement requirements are.met:
(1) PT-67, Weekly Reading of the Motor Timer; (2) CH-E-P-Nl On Demand Oil Sample; and, (3)
CH-E-P-N2, On Demand Oil Chang Additionally, administrative controls to implement Instrument Department QDR maintenance require-ments were in the approval proces Based on the licensee revising the QDR and implementing administra-tive controls and procedures to ensure the lube oil is sampled/
replaced, this item is considered close (Ctosed) VIO 280,281/86-12-05, Raychem Splice Sleeves in Unqualified Configurations (TI 2500/17);
(Closed) 281/LER 86-35, 281/LER 86-18, Improperly Installed Splices in EQ Equipment Due to Inadequate Procedures;
(Closed) VIO 338,339/87-32-05, Raychem Splices in Unqualified Configurations (TI 2500/17).
Previous inspections at both SPS and NAPS identified Raychem splices in unqualified configuration The splices at SPS were identified prior to the issuance of IEN 86-53 in June 198 The licensee, in response to IEN 86-53 and the identification of the unqualified splices at SPS undertook an inspection program at both sites to evaluate all Raychem splices. Unqualifiable splices, those that fell outside of any industry test report, were identified at both site The licensee documented its findings i~ Technical Report EQ-0010, prepared JCOs for those splices that fell outside their acceptance criteria, and issued Technical Report EQ-0038, "Review of Raychem Splices Outside the Operability Criteria for Surry Units 1 and Subsequently, the splices were replaced in accordance with the Specification for Electrical Install at ion for Surry Power Station Units 1 and 2 (NUS-2030, Rev. 4) or the Specification for Electrical Installation ~orth Anna Power Statiori Units 1 and 2 (NAS-3014, Rev. 3, EWR 0378).
All splices made after the licensee's inspections have been made using these procedures which implement the acceptance criteria provided by Rayche During the walkdowns at each site, Raychem splices were inspecte There were no problems identified with the splices at NAPS, however, there were minor workmanship problems identified at SP These splices, made by the construction group, provided adequate sealing to prevent moisture intrusion, but there was excess material that was not properly shrun This indicated that additional emphasis was needed on the proper Raychem installation techniques and procedures for the construction craft and QC personne The three splices identified will be reworked using NUS-2030 during the upcoming Unit 2 outage and sp-lices made after the completion of IEN 86-53 inspections will be spot checked on both SPS units to see if there are additional problem Also, additional Raychem training will be provided prior to the SPS Unit 2 refueling outage scheduled for late August 198 Based on the acti ans taken by the 1 i censee, the review of the procedures governing Raychem installation, and the inspection of several splic~s, these items are considered close (Closed) VIO 280, 281/86-12-06, Unqualified Rockbestos Cabl A -previous inspection identified that qualification documentation was not provided to establish qualification for Rockbestos KXL-510 cabl A review of QDR 5.6.1 for Rockbestos cable showed that the proper documentation had been added to the file to qualify the cabl Based on the documentation being added to the file, this item is considered close *
4 (Closed) !FI 280,281/86-12-07, High Head Safety Injection Pump Motor Qualified Life A previous inspection identified that the calculated qualified life for the HHS! pump motor was 36 year The calculations had an over-conservative service temperatur Some of the conservatism was taken out and the qualified life recalculated. This is documented in Aging Calculation NE-30, Rev. 1, dated July 14, 1986, and shows a life of 58.23~ years based on a service temperature of 101.214°C at SP QDR S-4.1, "High Head Safety Injection (HHSI) Pump Motor," was revised on October 10, 1986, to include the new aging calculatio Based on the revised calculation and QDR revision, this item is considered close (Closed) !FI 280,281/86-12-08, Rockbestos KXL-760 Inclusion A previous inspection identified that the formulation of Rockbestos KXL-760 cable was not included in the QD The licensee had the information to show qualification, however, it was not in the QD The QDR has been revised (October 10, 1986) and the information necessary for qualification has been adde The item is considered closed * (Closed) IFI 280,281/86-12-09, Brand Rex Cable Similarity A previous inspection identified that there was no similarity analysis between the. tested and installed cabl During the inspection, the licensee provided information to show that the installed cable was of the same material and construction as that teste QDR S-6.13, "Brand Rex XLPE Insulated, Hypalon Jacketed, 600 V Power and Control Cable", was revised and review showed that the information necessary to demonstrate qualification had been adde The item is considered close (Closed) IFI 280,281/86-12-10, Marathon Terminal Blocks A previous inspection identified that Marathon terminal blocks were not clearly addressed in the Limitorque QDRs S-3.1 and During the licensee's inspection program to address the internal wiring of Limitorque actuators, terminal blocks were removed from the actuators and replaced with Raychem splice In order to show qualification prtor to the removal of the terminal blocks, the licensee revised the Limitorque QDRs to address the terminal blocks clearly. This was verified by the inspector and the item is considered close (Closed) !FI 338,339/85-06-02, TM! II.B.2 Equipment Qualification The TMI Action Plan item was left open to be evaluated during the EQ inspection for compliance with 10 CFR 50.4 The inspector reviewed the licensee's response, "VEPCO response to NUREG 0737 Post TMI
Requirements, Rev. 2", and the Environmental Zone Descriptions for NAPS Units 1 and The zone descriptions contain the calculations for radiation levels throughout the plan Based on the review of the above documents and the results of the EQ inspection documented in NRC Report Number 338,339/87-32, this item is considered close (Closed) VIO 338,339/87-32-01, EQ Maintenance Requirements Not Adequately Addressed in Station Procedure During a previous in's*pection, three maintenance procedures* were identified as not adequately addressing required EQ maintenance requirement This was due to inadequate reviews of the QDRs and inadequate procedural control The licensee had evaluated these three examples and either revised the maintenance procedure or removed the item from the EQ required maintenance statu The licensee has also revised ADM-3.10, Environmental Qualification Program, to include instructions that provide review guidelines for identifying and documenting changes in the QDR that require changes in the station maintenance procedure The licensee is in the process of reviewing all QDRs and developing a cross reference index of QDRs and Maintenance Procedures/
Requirement The cross reference should ensure that all required EQ maintenance are addressed and that only required EQ maintenance are in the QDR The cross reference for the instrument shop is in the typing cycle and the electrical shop is in the developement stag The licensee has committed to completing this cross-reference by October 31, 1988, and is tracking them on their Commitment Tracking Syste The tracking numbers are 02-87-5366-21 for the instrument shop, and 01-87-5366-22 for the electrical sho Base upon review of the instrument shop cross-reference manual that was submitted for typing and the commitments that are being tracked, this item is considered close (Closed) VIO 338,339/87-32-02, Unqualified Limitorque Operators A previous inspection documented that the licensee had identified that nine Limitorque motor operators were installed without documentation to substantiate qualificatio Proper evaluation were made for con ti nue.d opera ti o Subsequently, all the subject OIJ'erators have been replaced with fully qualified operator The licensee identified the cause of this to be a failure to include, as part of the procurement process, specific requirements for qualification documentation to be provided by the vendo Additionally, it was determined that there was a failure to perform a complete review of the procurement documentation prior to its inclusion in the QD The licensee is rev1s1ng procedure to add guidance to engineering standards and specifications for procurement requirement The procedures will require that purchased articles be documented to be qualified to specific test report The 1 i censee has committed to implementing the procedures by August 31, 1988, and is tracking the progress via CTS Number 01-87-5366-24 and 01-87-5366-2 Based on the licensee's actions and the tracking of the commitments, this item is close.
(Closed)
VIO 338,339/87-32-03, Performance Characteristics Not Adequately Address~d A previous inspection identified that performance characteristics of el ectri cal equipment important to safety were not adequately addressed in the QDR This was caused by the failure to require a summary of performance requirements in the QDR when the organization and format of the QDRs was develope The licensee has committed to revise Engineering Standard STD-GN-0025, "Equipment Qualification Standard", by August 31, 198 The* revision will clarify the format for addressing performance characteristics in the QDR Once the standard has been revised, the QDRs will be revised on a schedule that will have all QDRs revised by December 31, 198 The standard revision is being tracked under CTS Numbers 01-87-5366-26 and 86-5163-21 for NAPS and SPS, respectivel The revision of the QDRs is being tracked under CTS Numbers 01-87-5366-27 and 86-5163-22 for NAPS and SPS, respectivel The inspector reviewed the preliminary work that had been performed during the development of the plan to address perfonnance charac-teristic The preliminary work indicates that the plan developed should resolve the issu Based on the preliminary work and the commitments being tracked in CTS, this item is considered close (Closed) URI 338,339/87-32-04, Test Anomalies from Victorean Test Report Not Adequately Addrssed in QDR File A previous inspection identified that several test anomalies for the Victoreen high range radiation monitor at NAPS were not adequately addresse l'-he licensee revised the QDR to address all the test anomalies except for the performance characteristics which will be addressed during the project discussed abov This item is considered close.
Generic Letter Followup (92703)
The following items were reviewed in the Region II offices after receiving information from the license These items are related to Generic Letter 83-28, Salem ATWS Events (TI 2515/91).
- 7 (Closed) IFI 280,281/84-25-01, Procedure Revision A previous inspection identified two licensee procedures that differed in nomenclature for the same activit ADM Procedure 7 specified the use of work order forms for recording maintenance activitie ADM 79.7 specifies the use of both work order and maintenance report form The licensee committed to revised ADM-86 to reflect only the use of work orders, and to incorporate ADM-79.7-79.10 into ADM-7 The licensee submitted documentation which confirmed that ADM 79.7, 79.8, 79.9, and 79.10 have been incorporated into ADM 7 A review of procedure ADM-79.2 dated June 8, 1988, verified that work order packages are reviewed by planning and entered into the computerized work planning and tracking system (WPTS). This item is close (Closed) IFI 280,281/84-25-02, Instrument Instructions During Preventative Maintenance Activities The licensee was utilizing a chatillon 11 push-pull gauge" to measure force required to activate the trip bar on the reactor trip breaker The opera ti on of the gauge was not fully understood by the maintenance technician and no instructions for use of the gauge was available. The licensee committed to have instructions available and to include the operating instructions in the reactor trip breaker maintenance procedur Review of procedure No. PC-DB-E/Rl dated August 28, 1987, revealed that the procedure contained a requirement for the technician to read the Chatillon "Push-Pull Gauge" Instructions which is attached to the procedur Based of the above, this item is close (Closed) IFI 50-280,281/84-25-03, System and Component Safety-Related Classification List During site inspection on September 10-14, 1984, a review of licensee's procedure ADM-73, Classification of Systems, Components, and Structures, revealed that the procedure was too general and did not provide enough detail for classification of individual component The licensee had previously identified this limitation in Audit Report S84-30 and stated that they were in the process of revising the procedur They also stated that they were in the process of formulating a more detailed component listing by mid 198 LfcEfnsee 1 s 1e*tter to NRC dated July 26, 1985, stated that the development of new and more completed listing of safety-related components was in planning and was expected to be completed by the end of the second quarter of 198 The licensee's revised procedure ADM-73, dated June 30, 1987, has been expanded to include adequate detail for the classification of component NRC letter and Safety Evaluation Report dated March 29, 1988, requested the licensee notify NRC if they had not developed and implemented the new listing. Based on the above, this item is close ~--~~------~---i 8 (Closed) Unresolved Item 280,281/84-25-04, Audit of Technical Manuals During inspection of September 10-14, 1984, the inspector found that a vendor design change applicable to both Units 1 and 2 had only been attached to the vendor manual applicable to one Uni The licensee agreed to audit other manuals to determine if this was as isolated case or a weakness in their manual control procedur Subsequent to the above inspection, the licensee performed audit No. S84-37 vendor techni ca 1 manua 1 s; procedures, drawings, and purchase orders to ensure that vendor technical information was being received handled and utilized as require The licensee audit identified several problem areas which have been correcte Followup Audit Nos. S84-37A, S84-37B, and S84-37C dated December 12, 1984~
January 10, 1985, and November 21, 1985, confirmed that corrective action had been implemente Based on in office review of the above documentation, this item is close (Closed) IFI 50-280,281/84-25-05, Identification of Safety-Related Procedures A previous inspection revealed that licensee maintenance and operating procedures were not stamped or marked as safety-related or whether the procedure was a controlled documen The licensee has evaluated the importance of having procedures applicable to safety-related activities identified. Documents submitted subsequent to the inspection state that procedures are controlled by color coding the procedure as described in ADM-51 and that ADM-60 prescribes how.the procedures are prepared and reviewed prior to us Paragraph 7.3.8 of ADM-100 dated March 23, 1988, states that each preventative maintenance procedure shall be indicated 11Nonsafety-Rel ated" or "Safety-Re 1 ate Based* on review of ADM-100 and Station Commitment/Response Forms, this item is close (Closed) TI 2515/91, Inspection Followup to Generic Letter 83-28, Item Item 4.1 of Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events, required each licensee to review all vendor recommended reactor trip breaker modifications to ensure that the modifications had been implemente n---Z515/64-04.03C, Near-Term Inspection Followup to GL 83-28, required the regions to verify that the 1 icensee had evidence to demonstrate that vendor-recommended modifications were implemented on the reactor trip breaker TI 2515/91 provided guidance for performing inspection followup of licensee action on Item 4.1 of GL 83-28, Modification of Reactor Trip Breaker During regional inspection at North Anna (Inspection Report Nos. 50-338/85-11 and 50-339/85-11) the inspectors noted that modifications to the reactor trip system of Unit 2 had not been audited by the site QA group and that the audit would be performed on both units after all
,l t
modifications had been completed. Subsequent to this inspection, the licensee has completed the vendor recommended modifications to the reactor trip system, including the reactor trip breaker Examination of documents revealed that the modifications have been completed (Unit 2 on October 10, 1984, and Unit 1 on December 21, 1985) and that testing on the completed modifications were conducte Documents examined are listed below:
( 1)
(2)
(3)
(4)
(5)
(6)
(7)
( 8)
Design Changes Notice No. DC-84-04, Shunt Trip Attachment for Unit DCN Package included sign-off sheet Design Change Notice No. DC-84-05, Shunt Trip Attachment for Unit DCN Package included sign-off sheet Westinghouse Field Change Notice VRA0-40510 Material List for Automatic Activation Shunt Trip Panel for Installation in DB-50 Circuit Breakers Material List for Shunt Trip Attachment for Westinghouse type DB-50 Air Circuit Breaker Vendor Manual/File Indicator Form used to add changes to Westinghouse Reactor Trip Switchgear Manuals VEPCO Letter dated December 27, 1985 VEPCO Letter dated February 8, 1985, Confirmed Modification NCD-Elect-18 (Replacement of UVT Assembly) and WES-3023 (Removal of Overcurrent Trip Bracket) *
Based on the above, Item 4.1 of GL 83-28 and TI 2515/91 are considered close.
Exit foterview The inspection scope and results were summarized on June 24, 1988, with those persons indicated in paragraph 1 abov The licensee was informed that the items discussed in Paragraph 2 were considered close The licensee was notified by a telephone conservation on June 29, 1988, between, R. Krich, of your staff, and C. Paulk, NRC inspector, that the items dfs*cussed**in Paragraph 3 above were considered closed. Proprietary information is not contained in this report. Dissenting comments were not received from the license~. Acronyms and Abbreviations ATWS -
CFR -
-
Anticipated Transient Without Scram Code of Federal Regulations Commitment Tracking System
-
-
GL HELB -
HHS! -
!EN
-
I FI JCO
-
LER
-
MSLB -
MSVH -
NAPS -
-
-
-
-
TM!
VEPCO-VIO
-
WPTS -
XLPE -
Engineering Change Request Environmental Qualification Engineering Work Request Generic Letter High Energy Line Break High Head Safety Injection Inspection and Enforcement Notice Inspector Followup Item Justification for Continued Operation Licensee Event Report Main Steam Line Break Main Steam Valve House North Anna Power Station Notice of Violation Quality Control Qualification Document Review Site Engineering Office Surry Power Station Three Mile Island Virginia Electric Power Company Violation Work Planning and Tracking System Cross-Linked Polyethylene