IR 05000320/1978023
| ML19220B844 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1978 |
| From: | Haverkamp D, Sjostrom L, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B843 | List: |
| References | |
| 50-320-78-23, NUDOCS 7904270455 | |
| Download: ML19220B844 (4) | |
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U.S NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-320/78-23 Docket No.
50-320 Category B2 License No.
DPR-73 Priority
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Licensee:
Metrocolitan Edison Comoany P.O. Bo 542 Reading, Pennsylvania 19603 Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conduged:
June 15,1978 Inspectors:
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D ave,r"ang, Reactor' Inspector cate signed k
6/27/73
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L. C.~ Spi trom, Reactor Inspector
. date' si gned C k7 f7V C. Hf jins, Reactor Inspector datesigned Approved by: W A%n l 27/
D. M. Sternberg, Ayi.g Chief, Reactor date 41gned Projects Section No.1, RO&NS Branch Insoection Summary:
Insoection on June 15, 1978 (Recort No. 50-320/78-23)
Areas Insoected:
Routine, unannounced inspection of reactor vessel internais modifications; pipe restraints and supports; and 10 CFR Part 21 implementation.
The inspection involved 15 inspector-hours onsite by three NRC inspectors.
Results: No items of noncompliance were identified.
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7904270455-
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Reg 1on I Form 12 g
g'3. a,7 O (Rev. April 77)
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Metropolitan Edison Company
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No reply to this letter is required; however, if you should have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, O
E, don runner, ChD Reac' tor Operations and Nuclear Support Branch Enclosure: Office of Inspection and Enforcement Inspection Report Number 50-320/78-23 cc w/ encl:
R. L. Wayne, QA Manager, Design & Construction T. Brousaton, Safety & Licensing Manager R. W. Heward, Jr., Project Manager R. C. Arnold, Vice President, Generation L. L. Lawyer, Manager, Generation Operations - Nuclear G. P. Miller, Superintendent J. L Seelinger, Unit 2 Superintendent Gerald Charnoff, Esquire I. R. Finfrock, Jr.
Miss Mary V. Southard, Chainnan, Citizens for a Safe Environment (Without Report)
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SOP No. 2-78-061, " Installation of Source Retainer ORA's."
SOP No. 2-78-062, " Retainer Installation."
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Proc. No. 2502-1.3, " Main Fuel Handling Bridge."
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Proc. No. 2501-1.1, " Fuel Control Document. "
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Proc. No. 2303-M9, " Containment Monitor-RMS Channel Functional
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Test."
The procedures were reviewed for management approval, technical adequacy, Technical Specification confor nance, and proper implemen-tation.
No inadequacies were identified.
During the inspection the licensee removed the ORA's from the core, transferred them to storage and inspected various fuel assembly locking cups for wear with a remotely operated television camera.
The inspectors witnessed various portions of these evolutions.
Ne items of noncompliance were identified.
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Pioe Restraints and Succorts The inspector examined selected pipe hangers and restraints on several piping systems inside containment.
Two apparent pipe re-straint deficiencies were identified, including a loose steel support plate near mechanical snubber serial number 863 and a mechanical snubber (serial No. 411) with an excessive attachment angle.
Both deficiencies were located on the pressurizer secondary spray piping at the refueling deck level, and were discussed with licensee representatives.
The resolution of these hanger deficiencies will be rr 'iewed during a subsequent inspection.
(320/78-23-01)
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10 CFR Part 21 Imolementation The inspector reviewed the following items related to licensee im-plementation of 10 CFR Part 21 requirements.
Posted documents for informing employees of Part 21, Section
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206, and procedures adopted pursuant to Part 21, including the location where the regulations and procedures may be examined and to whom reports may be made.
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Selected purchase orders.
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Selected Nonconformance Reports
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These items were reviewed to verify the adequacy of the implementa-tion of Part 21 requirements / procedures / controls listed belcw.
Posting of requisite documents.
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Specification of the application of 10 CFR Part 21 provisions
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in applicable procurement documents issued af ter January 6, 1978.
Evaluation of deviations or conditions or circumstances, or
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failure to comply, not resulting in a report to the Commission.
Acceptance criteria for the above review included inspector judgtment and requirements of 10 CFR Part 21 and applicable licensee implementing procedures.
The inspector's findings regarding 10 CFR Part 21 implementation were acceptable.
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Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at tne conclusion of the inspection on June 15, 1978. The inspector summarized the purpose and scope of the inspection and the findings.
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e DETAILS 1.
Persons Contacted Metrocolitan Edison Cocoany Mr. M. Benson, Nuclear Engineer
- Mr. M. Bezilla, PORC Secretary Mr. W. Cotter, Supervisor of Quality Control Mr. J. Floyd, Unit 2 Supervisor of Operations
- Mr. J. Hilbish, Station Lead Nuclear Engineer Mr. F. Huwe, Health Physics Foreman
- Mr. J. Seelinger, Unit 2 Superintendent - Technical Support General Public Utilities Service Corocration Mr. J. Godleski, Quality Assurance Engineer The inspectors also talked with and interviewed several other licensee employees during the inspection.
They included control room operators, technical and engineering staff personnel and general office personnel.
- denotes those present at the exit interview.
2.
Reactor Ves'sel Internals Modifications Based on certain design deficiencies identified at other Babcock and Wilcox (B&W) facilities, the licensee is in the process of removing 38 of 40 orifice rod assemblies (0RA's) and adding re-tainers for burnable poison rod assemblies (BPRA's) and the remain-ing ORA's. The inspector reviewed the two B&W topical reports discussing the modification. The licensee is currently finalizing his license amendment request for submittal to the Office of Nue:sar Reactor Regulation.
The inspector also reviewed the following plant procedures being used to effect the modification:
50P No. 2-78-058, " Controlling Procedure for ORA /BPRA
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S0P No. 2-78-059, " Manual ORA Removal."
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S0P No. 2-78-060, " Fuel Assembly Locking Cup Inspection."
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