IR 05000443/1986024
| ML20210U741 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/21/1986 |
| From: | Gregg H, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20210U739 | List: |
| References | |
| 50-443-86-24, NUDOCS 8606030067 | |
| Download: ML20210U741 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report.No. 50-443/86-24 Docket No.
50.443 License No. CPPR-135 Priority --
Category B Licensee:
Public Service of New Hampshire P.O. Box 330 Manchester, New Hampshire 03105 Facility Name:
Seabrook Station, Unit 1 Inspect.fon At:
Seabrook Station, Unit 1
Inspection Conducted: April 14 - 18, 1986
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Inspector: -
v ev f 2/
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. Grigg, Lead /Rpctor Engineer
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Approved by:
M J Lta,s,r _
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b J. Wi/fginsTChief(yerial and Date Pk6 cesses Sectten,4DRS Inspection Summary:
Inspection of April 14 - 18, 1986 (Report 50-443/86-24)
Areas Inspected:
Routine unannounced inspection of the licensee's records related to the reactor vessel and internals and the licensee's activities related to previously identified items.
Results: No violations were identified.
8606030067 860528 PDR ADOCK 05000443 G
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Of: TAIL,j 1.0 Persons Contacted 1.1 New Hampshire. Yankee (N_i!Y1
- S. Buchwald, QA Supervtsor
- R. Cyr. Maintenance Manager
- W. Johnson, Vice-President, Quality Programs
- J. Marchi, Startup OC A*anager M. Rubano, Asst. Startup Test Engineer
- W. Sullivan, Senfor QA Ecgiheer
- J. Tef ft, Startuo Engineer 1.2 Yankee Atomic Electricjornpany (VAEC)
M. hyther, Startup QA Engineste O. 1yrich, Startup OA Engineer
'W. Hiddleton, QA Staff Engineer
- D. Perkins, QA Engineer V. Sanchez, Licensing Engineer
- J. Singleton, Asst QA Manager J. Watts, Startup OA Engineer 1.3 Westingheuse -Nuclear Operatfor.s Divig_on C. Rausch, Mechanical Engineer C. Walker, Systems Engineer 1.4 UnitedEngineersandConstructors(USCJ
- B. O'Connor, Field Supervisnr QC S. Wolfra'n, Mechanical Engineer
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1.5 U.S. Nuclear Regulatory Co$ mission
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- R. Barkley, Resident inspector
- 0. Ruscitto, Resident Inspector
- Denotes presence at exit ineeting.
2.0 Reactor Vessel and Reactor Internals Rec ges. Review
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The inspector performed a review of Reacter (Rx) vsssel and internals records pertaining to receipt, assenBly, materiais, audits, nonconform-ances and deviations to determine tne adequacy of the licensee's record
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system. Also, the review included work perfonned, problems encountered
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and the subsequent dispcsitions as noted f n the records.
During this review, the inspector interfaced with Westing'nouse (W), NHY Startup and
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Startup QA, YAEC QA, UE&C Engineering, and Ser.brcck Yankee Document Control Center (SBYDCC). The inspector toured the primary containment to observe the Rx vessel and internals.
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2.1 Documentation Reviewed The specific documentation reviewed during this inspection included:
W "A-Specification" - 4 Loop Standard Rx Internals Assembly Pro-
cedure (2463 A68-601), current status of the internals assembly, and the listing of deviations.
Nuclear Installation Services Company (NISCO) engineering
specification for the Rx vessel internals assembly (ES 4031-PSCNH-10).
UE&C Rx vessel upper and lower internals receiving data package
and associated Nonconformance Reports (NCRs) and their dis-positions.
Seabrook Station Rx Post Hot Functional Inspection procedure
(1-PT(I)-43), and associated NCR findings and their disposition.
Audits of W Pensacola and NISCO pertaining-to Rx internals and
QA adequacy, (YAEC SA 537 WO17, SA 713 CS271, and SA 654 CS236).
Records of Rx vessel and internals maintained in the SBYDCC.
- Current status of NCRs and FDRs, including review of completed
items.
2.2 Records System During the review of the Rx vessel and internals records, the inspec-tor determined that the licensee's system for preparing, reviewing, maintaining, and retrieving records is acceptable.
Each of the records reviewed accurately reflected the work performed; NCRs and FDRs accurately described problems; rework / repair was fully defined and ar disposition was appropriately performed and evaluated by cog-nizant personnel.
2.3 Organizations Involved The organizations involved with the Rx vessel and Rx internals included Combustion Engineering (supplier of vessel and head), W Pensacola (supplier of Rx internals), NISCO (installer of Rx inter-nals), UE&C (overview of Rx internals receipt and installation), and W N00 (overview of both Rx vessel and Rx internals). The organiza-tions' records were reviewed and were determined to have appropriate control and overvie f:
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2.4 Record Maintenance and Retrieval The inspector reviewed the record maintenance and retrieval system.
Each item requested was readily retrievable and copies of these records were provided to the' inspector.
2.5 Current Status of Rx Vessel and Internals The inspector determined there are no open NCRs or FDRs on the Rx vessel and a W Quality Release had been issued.
Two NCRs or FDRs remain open on the Rx internals:
item DN 13663 on head adapter plugs appears to be a paperwork problem and item FDR-NAHM-1059 which pertains to support pin weld corrosion requires further review.
The remaining steps to be performed to complete the W A-Specifi-cation. requirements include guide tube cleaning and boroscoping, upper internals cleaning and inspection, and baffle gap inspection.
Upon completion of all steps, W - NOD will issue a Quality Release.
Therefore, a management control system is in place to complete all remaining items.
The final item which remains to be completed is to place the Rx vessel and internals into the required cleanliness status. The inspector determined that cleanliness requirements are established.
within the licensee's system and are stated in the Startup group's resolution to the PT(I)-43 cleaning exception.
2.6 Findings Each of the areas reviewed during this inspection and mentioned above were determined to be acceptable.
No violations were identified.
3.0 Licensee's Activities Related To Previously Identified Items The inspector reviewed the licensee's responses and corrective actions
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taken to complete the closeout of the following previously identified items.
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3.1 (Closed) Unresolved Item 85-01-03, relating to Reactor Vessel (RV)
Internals: Availability of Certified Material Test Reports (CMTRs),
differences between FSAR Table 5.2-4 and actual materials, and absence of a weld reject disposition.
The inspector met with cognizant licensee personnel and discussed the licensee's May 22, 1983 response to this item. The inspector verified the Quality Release form for the RV internals, prepared by the vender Westinghouse (W) Pensacola, included verification of CMTRs and that
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the vender-is required to maintali,n then.
CMTRs for the adapter plugs
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which are welded to the vesse'i head were avatlable and, as committed to by the licensee, are in the process of being placed in data package QR 22443.
The inspector also vertfied that FSAR Table 5,2-4 has been revised to reflect the appropriate RV internals raaterials.
i The~ inspector reviewed. radiographic inspection report No. 0731 and verified that the disposition of weld locaticn 31-34 was acceptable based on e re-radiograph.
The licensee provided the inspector with details of their record
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system commitments and examples of meetirg the record retaining i
provisions of ANSI N45.2.9.
The inspector determined that the record retention system meets the licensee's coenitment to the ANSI standard.
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This item is closed.
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3.2 (Closed) IE Circular 80-CI-12 (including supplenental data of IE Information Notice 85-67), " Valve-Shaft-To-Actuator Key May Fall Out
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of Place When Mcunted Selow Horizental Axis".
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The inspector reviewed the licensee's resportse [0E&C letter of Nov. 25, 1985) which discussed the 'Seabrook butterfly valve actuator-to-key designs.
The licensee described the design for the rnajority of these valves as having standard square keys which are prevented
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from falling out of their keyways as the valve actuator mst be-removed before the key is exposed. The remaining butterfly v.alves have either splir,ed shafts (no keys) or Wo:odruff keys (with semi
circular ends captive in a keyway that has seni circular ends).
Again, in these cases, the connector or actuator must be removed from the shaft for a shaft-to-actuator disconnect to occur or to have a key faltout.
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The inspector determined that the licensee's butterfly valves are j
Posi-Seal (P0 24848) or Fisher (P0 2845) and are not the Pratt valves mentioned in the Ctreular. The inspector examined several Post-Seal
valves in the Primary Auxiliary Building at elevation 25' (vtives i
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1-CC-V0005, 1-CC-V299, 1-CC-V301, and 1-CC-V0006) and verified that i
each key could not fall out without removal of the actuator.
This item is closed.
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4.0 Exit Meeting
The inspector met with the licensee's representatives (Ider,tified in paragraph 1.0) on April 18, 1986, to summarize the findings of this
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inspection. NRC Resident Inspectors D. Ruscitto and R. Barkley were also
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in attendance.
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k During this inspeccion, the inspector did not provide any written l
material to the licensee.
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