IR 05000369/1980015
| ML19331E136 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 07/28/1980 |
| From: | Donat T, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19331E133 | List: |
| References | |
| 50-369-80-15, NUDOCS 8009050550 | |
| Download: ML19331E136 (5) | |
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UNITED STATES 3 (f'T,,o
NUCLEAR REGULATORY COMMISSION
/.E REGION 11
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101 MARIETTA sT N.W., sulTE 3100
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o ATLANTA, GEORGIA 3o303
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Report No. 050-369/80-15
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Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Unit #1 Docket No. 050-369 License No. CPPR Inspection at McGu're site on Lake Norinan Inspector:
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T.J.Donap f/
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Approved by:
//Y 7 /2d cff R. D. Martin, Section Chief, RONS Branch Dpe Sigrie~d SUMMARY Inspection Dates: June 9 and 10, 1980; June 17 and 18, 1980 Areas Inspected j
This routine unannounced inspection involved 36 inspector-hours on site in the areas of preparation for hot functional testing, preoperational test witnessing, review of licensee's responses to bulletins and circulars, review of previous inspection findings, and participation in the Emergency Planning review team audit.
Results In the areas inspected, no stems of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
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Licensee Employees
- M. D. McIntosh, Plant Manager
- E. Estep, Associate Licensing Engineer
- G. Gage, Operation Superintendent
- D. Lampke, Assistant Licensing Engineer L. Weaver, Performance Engineer M. Pacetti, Test Engineer M. Kitlan, Associate Test Engineer Other licensee employees contacted involved technicians, operators, security force members and office personnel.
Other Organizations
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E. M. McP
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Office of Nuclear Reactor Regulation, Emergency Respense Plan a.eview J. Sears, Office of Nuclear Reactor Regulation, Emergency Response Plan Review Team Leader
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 18, 1980, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Closed - Unresolved Item 78-10-01 concerning allegations that Duke Power Company had performed inadequate and incorrect or misleading design calcula-tions for the dropped spent fuel cask accident. The matter has been previ-ously resolved and documented in IE report 50-369/78-20, 50-370/80-15, dated August 7,1978.
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Unresolved Items Unresolved items were not identified during this inspection.
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Evaluation of Licensee's Emergency Response Program The inspector accompanied the joint NRR/IE Emergency Response Preparedness review team on its tour of the Unit 1 portions of the control room, the technical support ceraer, the operational suoport center, the shift super-visor's office, the pcf mary coolant sample room, the counting room, the meterology tower, and the personnel decontamination and first aid room.
e o-2-Also, the following near site facilities were inspected: the environmental monitoring station, the proposed location for the emergency operation center (crisis management center) and the training center.
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The inspector participated in the review team's mee' ting with licensee emergency planning representatives in order to identify those areas of the McGuire Emergency Response plan which needed additional information or clarification. On the evening of June 18, 1980, the inspector participated
.as a member of the emergency response preparedness review team at the Public Meeting on the Emergency Planning for the McGuire Nuclear Station held at the McGuire Training Center.
The inspector had no comments on the status of the licensee'.: Emergency Preparedness program or its implementation at the McGuire Nuclear Station.
The conclusion and recommendations of the review team will be provided in a separate report.
6.
Review of Hot Functional Test Program The inspector reviewed the status of preoperational test procedures concerned
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with the second hot functional test sequence. This iceluded verification that all necessary procedures had been approved for use by the station's Safety Review Committee (SRC) and that the necessary initial conditions had l
been signed and dated by cognizant licensee personnel.
i The inspector did witness the performance of TP/1/A/1150/16A Annulus Venti-lation Test.
The test procedure was reviewed to insure that all prerequisites had been satisfied.
The inspector discussed the test with the test engineer and observed the conduct of the vacumn blead down rate portion of the test.
The inspecor observed the licensee's inspectica of the door seals and his evaluation of the test data. The inspector's findings were clear'in this area.
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Review of Status of Licensee Response to IE Bulletins and Circulars Closed - n.Bulletin 79-15 on Deep Draft Pumps - The licensee responded August 30, 1979, that no deep draft pumps were installed in safety related systems at the McGuire Nuclear Steam Plant. The inspector verified the information provided and this bulletin is closed.
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Closed - IE Bulletin 79-16 on Vital Access Controls - The licensee, in their response dated June 18, 1980, stated that the subject of the adequacy of vital access controls had been addressed in their Site Security Plan which was under review by NRC's Office of Nuclear Material Safety and Safeguards.
The bulletin is considered c1csed because the subject is presently undergoing review by a separate NRC organization.
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-3-Closed - IE Bulletin 79-17 on Pipe Cracks in Stagnant. Borated Water Systems at BWR Plants - Not applicable to McGuire Nuclear Steam Plant which is a PWR facility.
Closed - IE Bulletin 79-24 on Frozen Lines in Safety Systems - The inspector reviewed the licensee'.s response dated October 31, 1979, in which they committed to insulate and heat trace the vent, recirculation, and level detection piping associated with the Refueling Water Storage Tank. The inspector reviewed the installation drawings for the modifications, and visually sited the affected piping.
Heat trace wires were visible on all sections of the piping except for a six foot portion of the recirculation piping. This was identified to the licensee, who had it corrected.
The bulletin is considered closed.
Closed - IE Bulletin 80-11 - Masonry Wall Design - This bulletin was not issued for licensee action at the McGuire Nuclear plant. The review of the licensee's submittals in response to IE Bulletins 79-02 and 79-14 will also cover the application of supports to masonry surfaces.
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Closed - IE Bulletin 80-12 - Insuring Decay Heat Removal Capability - This
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bulletin was also issued only for facilities with an operating license and is not applicable to McGuire. However, the technical specification changes necessary to assure diverse redundant means of decay heat removal will be incorporated prior to issuance of an operating license on Unit 1.
The inspector verified that the following IE circulars had been received at the facility and routed to the appropriate management representative for action:
79 13 Replacement of Diesel Fire Pump Starting Contactors 79-17 Contact Problem in SB-12 Switches on G. E. company Metal Clad
Circuit Breaker 79-18 Proper Installation of Target Rock Safety-Relief Valves 79-19 Loose Locking Devices on Ingersoll-Rand Pumps 79-20 Failure of GTE Sylvania Relays 79-22 Stroke Times for Power Operated Relief Valves 79-23 Failure of Moter Starters and Contactors to Operate 79-24 Proper Installation and Calibration of Core Spray Pipe Break Detection Equipment in BWP's 80-02 Nuclear Plant Staff Work Hours 80-07 Problems with the HPCI Turbine Oil System at BWR's 8.
Followup on Previous Inspection Findings and Opened Items a.
Closed Open Item 79-06-03 which concerned the need for administra-
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tive guidance on the proper method of documenting valve checklists when mere than one operator performed the veri-fication. Station Directive 3.1.28, Rev. 3, dated 2/26/80 states in Paragraph 3 that when multiple operators each perform on a portion of a valve checklist that a master copy of the checklist will be maintained by the shift supervisor
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e-4-e and will be marked upon completion by the operators who will also attach their working copy of the valve checklist to the back of the master copy.
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Closed -
Inspector Followup Item 79-13-01 on cleanup of the resin inadvertently added to the reactor coolant system.
The inspector reviewed the licensee's actioni, including fluthing the NC system and considers the item closed.
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Close'd - Open Item 79-13-02 on adding the diesel generator battery, which provides excitation and control power to the diesel generator, to the plant's Technical Specifications.
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" proof and review" copy of the Technical Specifications, dated June 20, 1980, has added surveillance requirement 4.8.1.1.4 concerning weekly checks of the. diesel generator battery condition. The addition of these surveillance steps closes this item.
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Closed -
Inspector Followup Item 80-03-04 concerned changing PT1/A/
4151/02 to include measuring valve closure timing for PORV valves INC-32A, INC-34A, and INC-36A. The inspector reviewed
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Revision I to the periodic test dated June 16, 1980, which incorporated the measurement of the closure time.
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Inspector Followup Item 80-03-06 concerning whether the licensee evaluated the problems encountered with Cutler-
' dammer type B26-MF relay decks for potential Part 21 reporting. The licensee has performed their evaluation and
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submitted a report to the commission in accordance with 10 CFR 50.55(e).
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