IR 05000293/1987013
| ML20212J370 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/02/1987 |
| From: | Anderson C, Pullani S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212J329 | List: |
| References | |
| 50-293-87-13, NUDOCS 8703090015 | |
| Download: ML20212J370 (9) | |
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.U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-293/87-13 Docket No.
50-293 License No. DPR-35 Category C Licensee: Boston Edison Company M/C Nuclear 800 Boylston Street
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Boston, Massachusetts 02199 Facility Name: Pilgrim Nuclear Power Station Inspection At: Plymouth, Massachusetts Inspection Conducted:
February 10 - 13, 1987 Inspector:
2!2hQ 5. V. Pu]IanMead Reactor Engineer date Approved by: '
92 C.JyAnderson, Chief,PlantSystems date Inspection Summary:
Inspection conducted on February 10-13, 1987 (Report No.
50-293/87-13)
Areas Inspected: Routine announced inspection of the plant modifications for the Analog Trip System (ATS),10 CFR 50 Appendix R and the Emergency and Plant Information Computer (EPIC), including review of post-modification test procedures and test results.
Results: No violations, deviations or other unacceptable conditions were identified.
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8703090015 B70226 PDR ADOCK 05000293 G
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DETAILS 1.0 Persons Contacted 1.1 Boston Edison Company (BECo)
- M. Akhtar, Group Leader, Modification Management R. Barry, Computer Group Engineer L. Beckwith, Compliance Engineer
- M. Brosee, Maintenance Section Manager R. Grazio, Section Manager, Site Engineer
- P. Hamilton, Senior Compliance Engineer
- J. Keys, Regulatory Affairs Group Leader R. Kirven, Senior Electrical Engineer
- D. Mills, Construction Management Group Leader A. Morizi, Assistant Director, Outage Management J. Peters, Senior Construction Engineer
- J. Poorbaugh, Senior-QA Engineer
- K. Roberts, Nuclear Operations Manager / Director Outage Management
- R. Sherry, Chief Maintenance Engineer i
W. Sullivan, Senior Fire Protection Engineer
- R. Velez, Appendix R/ Fire Protection Manager
- F. Wozniak, Fire Protection Group Leader 1.2 Nuclear Regulatory Commission (NRC)
- P. Bissett, Reactor Engineer W. Cooper, Radiation Specialist, Region II
- J. Lyash, Resident Inspector M. McBride, Senior Resident Inspector R. Nimitz, Senior Radiation Specialist
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- C. Petrone, Lead Reactor Engineer 2.0 Followup of Previously Identified Items (Closed) Inspector Followup Item (85-27-45) Lack of Similarity Analysis in EQ Files for Installed and Tested Solenoid Valves The model numbers for 4 installed Post Accident Sampling System (PASS)
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solenoid valves in the plant (SV-5065-63, 64, SV-5065-69 and 70) diferred
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from the test model used to establish Equipment Qualification (EQ).
However, there was no similarity analysis available in the EQ files for inspector's review during the inspection 85-27.
Subsequently on November 1, 1985, the licensee performed the required analysis and filed it in the EQ files. The inspector reviewed the analysis and found it acceptable.
Based on the above, this item is considered closed.
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(Closed) Inspector Followup Item (85-27-46) 0-Ring Replacement on PASS Valves.
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During inspection 85-27,.the inspector had identified that the manufacturer for the 4 PASS Valves discussed in item 85-27-45 above had recommended that the 0-rings in the valves be replaced once every 5 years, but this
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replacement requirement was not addressed in.the EQ files. The licensee
subsequently added a justification in the EQ files for not replacing the
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0-rings. The manufacturer's EQ test program showed that the 0-rings were
good for 40 years. The 5 year replacement schedule was based on the 0-ring supplier's recommendation It was not a requirement to maintain equipment qualification.
This item is considered closed.
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(Closed) Inspector Followup Item (85-27-49) Radiation E.wosure Data for Detectors Not Contained in EQ Files
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During inspection 85-27, the inspector identified that radiation exposure data for 4 Containment High Range Radiation Monitors RE 1001-606 A and B (for drywell) and RE 1001-607 A and B (for suppression pool) was_not i
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contained in the EQ files.
This data was needed to establish the qualification of the detectors to assess the effect of radiation on the
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detectors. The licensee subsequently added the required data to the EQ
. files. The inspector reviewed the' data and found it acceptable.
This item is closed.
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- [ Closed)UnresolvedItem(84-15-05) Recent Minor Fire Incidents
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Several minor fire incidents were reported during the 1984 outage for i
replacement of the reactor coolant piping in the drywell. These fires
were initiated by sparks from cutting and welding operations. During the i.
previous inspection (84-15), the licensee had committed to be more
aggressive in the implementation of the existing fire prevention and house
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keeping procedures and to take immediate action to develop a plan aimed at eliminating or drastically reducing fires at the facility.
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Subsequently, the licensee has implemented an aggressive program to monitor the hazards posed by hot work (cutting, welding & grinding). A i
full-time fire inspector staff monitors these activities around the clock.
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at all other times. These inspectors have been given the full authority i
of the Fire Prevention and Protection Officer to stop any hot work job that does not meet procedural and regulatory requirements. These
inspectors also monitor and control transient combustible loading in the station, including the use of flammable and combustible liquids.
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A daily log is kept which documents the status of Hot Work Permits.
Each inspector's shift activities are documented and retrievable in the Fire Inspector's Log Book which is available to the Fire Prevention and Protection Officer. These logs serve as a tool for management to identify and correct recurring problems with respect to hot work.
Based on the above, this item is considered closed.
3.0 Inspection of Plant Modifications The purpose of this inspection was to ascertain that the plant modifications for the Analog Trip System (ATS) and those required for 10 CFR 50 Appendix R and the new EPIC process computer are being implemented properly. These modifications are currently in progress and are at various stages of completion.
The inspector reviewed selected portions of the modification packages and associated documentation and the completed portion of the =cdifications to ascertain that they are being implemented properly. The scope of
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inspection included the following areas:
a Review of the modification packages to verify that they complied with the related licensee commitments and requirements.
- Implementation of the modifications to ascertain that they were conducted in accordance with appropriate specifications, drawings, and other commitments.
Post-modification testing was conducted in accordance with technically adequate and approved procedures.
- Adequate quality assurance, including proper administrative controls, were in effect for the above activities.
The details of the above areas of inspectior, are discussed below.
3.1 Review of the Modification Packages Inspector reviewed the following modification packages:
87-40, Detailed Design for Analog Trip System, Revision 0
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84-03D, ADS Modifications, Revision 3
84-03F, EDG Modifications, Revision 4
85-41, Torus Water Level / Temperature, Revision C
86-45, Emergency Lighting, Revision A
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83-51A, Installation and Monitoring of EPIC Equipment, Revision 0
86-45, Emergency Lighting, Revision A
83-51A, Installation and Monitoring of EPIC Equipment, Revision 0
83-51B, Installation and Termination of Data Acquisition System Wiring in Control Room and Cable Spreading Room, Revision 0
83-51C, Installation and Termination of Data Acquisition System Wiring in Existing Process Computer Room Panel, Revision 0
83-510, EPIC System External Cable Installation, Revision 0 These modifications are being implemented as major plant design changes in accordance with Nuclear Engineering Department Procedure NED 3.02, Preparation, Review, Verification and Revision of Design Documents for Plant Design Changes, Revision 14. The inspector reviewed the procedure and the modification packages to verify that sufficient administrative controls existed for the activities associated with the modification and that these controls were in effect.
Specifically, the review was to ascertain that the following controls exist:
Procedures for control of the modifications, including methods for initiating design changes; and methods to assure tha+ the modification does not involve an unreviewed safety question.
- Procedures and responsibilities for design control, including organizational responsibilities; review of design and modification program; methods for conducting safety evaluation, reviewing and approving design input requirements and performing independent verification; training of personnel performing modification activities; and auditing design activities
Administrative control for design and document control, including interdepartmental interface; record storage; implementation of approved design changes in accordance with approved procedures; post-modification acceptance testing; and post-modification acceptance criteria No unacceptable conditions were identified.
The inspector reviewed selected portions of the modification packages including associated engineering drawings and vendor manuals. The scope of review was to ascertain that the packages were technically adequate and complied with the related licensee commitments and NRC requirements.
No unacceptable conditions were identified.
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3.2 Implementation of the Modifications The inspector reviewed selected procurement and installation documents to verify that they complied with the appropriate standards, specifications and drawings. The inspector also toured
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and visually inspected completed portions of the modifications to ascertain that the installation was as specified in the drawings.
No unacceptable conditions were identified.
3.3 Post-Modification Testing The inspector reviewed the post-modification test procedures listed in Attachment 1 and the test results of procedures identified by an asterisk (*) in Attachment 1.
In addition, the inspector reviewed Nuclear Operations Department Procedure N001.3.4, Procedures, Revisions 29, which is the administrative control procedure for
preparation of all procedures. The scope of the above review was to i
ascertain that:
Appropriate administrative controls were in effect for the
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preparation and performance of the test procedures.
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The test procedures were technically adequate to functionally
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. verify the operability of the modified systems.
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The independent reviews were performed to determine the
adequacy of the procedures.
The procedures were approved by the Operations Review Committee
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The test was performed in accordance with the approved procedures.
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The test results met the specified acceptance criteria.
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No unacceptable conditions were identified.
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3.4 Quality Assurance
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The scope of inspection included a verification that the
modification is being 'mplemented in accordance with the quality assurance requirements of the following documents:
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10 CFR 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants.
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Pilgrim Quality Assurance Manual.
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- Nuclear Engineering Department Procedure NED 3.02; Preparation, Review, Verification and Revision of Design Documents for Plant Design Changes; Revision 14.
- Other requirements and licensee commitments.
No unacceptable conditions were identified.
f 4.0 Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, violations or deviations.
5.0 Exit Interview The inspector met with licensee management representatives (see Section 1.0 for attendees) at the conclusion of the inspection on February 13,
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1987. The inspector summarized the scope and findings of the inspection at that time.
The inspector and the licensee discussed the contents of this inspection report to ascertain that it did not contain any proprietary information.
The licensee agreed that the inspection report may be placed in the Public Document Room without prior licensee review for proprietary-information (10 CFR 2.790).
At no time during this inspection was written material provided to the licensee by the inspector.
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Attachment 1 List of Post-Modification Procedures Reviewed 1.
Analog Trip System Post-Modification Test Procedures
- TP86-06, Pre-operational test of modifications on RPS analog trip cabinets C-2228A1 & A2 and C-222981 & B2, Revision 3
- TP86-09, Pre-operational test of ECCS analog trip cabinets C-2233A and C-2233B, Revision 1 TP86-11, Common zero reference for LI-263-101, LR-640-28, LR-1001-604 A&B, and LI-1001-650 A&B, Revision 0 TP86-12, ATS loop test of C129 A&B racks transmitters, Revision 0 TP85-18, ATS loop test of C2205 rack transmitters, Revision 0 TP86-19, ATS loop test of C2206 rack transmitters, Revision 0 TP86-22, ATS loop test of C2252 rack transmitters, Revision 0 TP86-23, ATS loop test of C2256 A&B, Revision 0 TP86-25, Locally mounted transmitters, Revision 1 TP86-72, ATS-ECCS powe' supplies and control room alarms, Revision 0 2.
Appendix R Post-Modification Test Procedures
- TP86-135, Preoperational Test of the Standby AC Power System (Diesel Generator A), Revision 2
- TP86-143, Preoperational Test of the RHR, AOS, Core Spray and Miscellaneous Equipment Functional Tests, Revision 3
- TP86-156, Preoperational Test of Motor Control Center B15, Revision 0
- TP86-159, Preoperational Test of the Standby AC Power System (Diesel Generator B), Revision 0
- Completed test results of these procedures were reviewed by the inspector.
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EPIC Post-Modification Test Procedure A selected sample of " EPIC signal Cut-in Worksheets" used to " cut-in" computer points were reviewed by the inspector. The integrated test procedure to check out overall operation of the EPIC after installation is not yet developed by the licensee.
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