IR 05000471/1979001

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IE Insp Rept 50-471/79-01 on 790207-09.No Noncompliance Noted.Major Areas Inspected:Qa Activities Re Receiving, Handling & Storage of safety-related Components & Licensee Action on Previous Insp Findings
ML19241B119
Person / Time
Site: 05000471
Issue date: 03/19/1979
From: Mattia J, Mcgaughy R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19241B107 List:
References
50-471-79-01, 50-471-79-1, NUDOCS 7907110703
Download: ML19241B119 (4)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-471/79-01 Docket No.

50-471 Liccnse No.

Priority Category A

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l Licensee:

Boston Edison Comoanv

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800 Boylston Streat Boston, Massachusetts 02199 Facility Name:

Pilarim Nuclear Generatino Station, Unit 2 Inspection at:

Plymouth, Kingston and Boston, Massachusetts Inspection conducted:

February 7-9, 1979 Inspectors:

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'. Mattia, Reactor Inspector cate signed

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date signed I

da signed Approved by: d 4/ /v< <Fmo,L

  1. <1er /1.47d R. W. McGaugny'

'ef, Projects Section,

' c' ate /s i gned RC&ES Branc..

Insoection Summary:

Inspection on February 7-9,1979 (Recort No. 50-471/79-01)

Areas Inspected:

Routine, unannounced inspection o' quality assurance activities associated with receiving, handling and storage of safety-related components.

The inspector also reviewed licensee action on previous inspection findings.

The inspection involved 14 inspector-hours on site by one NRC inspector.

Results:

No items of noncompliance were identified.

7007110703 Region I Form 12

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(Rev. April 77)

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DETAILS 1.

Persons Contacted Boston Edison Company

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W. Anderson, Project Engineer D. Eryant, Project Engineer R. Butler, Nuclear Projects Manager

  • M. Sides, QA Manager

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  • M. Yessaillan, QA Procurement Group Leader

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Bechtel Corcoration R. MacDonald, Responsible Field Engineer R. Matthews, Materials Control Supervisor i

denotes those present at the exit inter iew i

2.

Licensee Ac r.a on Previous Insoection Findinas (Closed) Unresolved Item (471/78-01-01):

The inspector verified that the licensee conducted a review of the C. E. Avery's (fabricator of l

reactor internals) QA Manual to determine that it conformed to PSAR

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commitments.

The licensee reviewed the QA Manual during an audit

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(BECO Audit #78-19) of C. E. Avery.

The QA Manual conformed to ASME Section III (NCA 4000) and was approved.

The licensee also revised his QA program to include their audit findings known as " Action Items".

Their procedure, number 19.01 entitled, " Action Item Follow Program" was deleted and a new procedure, number 18.03 was issued on November 24, 1978 to include " Action Items" in their 18 criteria QA program.

This item is considered resolved.

(Closed) Unresolved Item (471/78-01-02):

The licensee stated that the Responsible Field Engineer who is performing the meggering of the safety-related motors is not covered by the ANSI N45.2.6 Standard.

However, the licensee observed (BECO Inspection Report No.79-011, the Field Engineer performing an insulation resistance test and confirmed that the man was proficient.

The inspector reviewed several insulation resistr e test reports to verify that the correct test voltage was used.

This item is considered resolved.

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3.

Project Status Design work by Bechtel is 55% complete as of January 15, 1979.

Their engineering progress is as follows:

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l Total Number Required Completed

System Descriptions

63

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Specifications 360 228 Drawing 5750 917 Procurements 222

Design work by Combustion Engineering, the NSSS, is mpproximately 851 complete. The status of major equipment by the NSSS is as follows:

Reactor Pressure Vessel and Pressurizer complete Primary Coolant Pumps 90% complete Steam Generators 92% complete Reactor Coolant Piping Complete 4.

Storage of Safety-Related Ecuicment The licensee currently has two warehouses where safety-related and non-safety-related equipment is being stored.

The inspector examined records and work activities of safety-related equipment in accordance with vendor instructions, Bechtel procedu.es and regulatory requirements.

The following safety-related equipment hr.s been received and is stored at the warehouses:

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safety injection motors (tag nos. 2-F-314A and 315A)

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charging pumps and notors (tag n.is. 2-P-302A, B and C)

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equipment drain pump (tag nos. 2-P-305A)

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boric acid pump (tag nos 2P-303A and B)

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holdup tank pumps (tag nos. 2P-309A and B)

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reactor coolant pump supports (tag no. 2S-218)

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pulsation damper (tag no.25-301)

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The inspector examined the storage of all the above equipment and randomly selected several of the maintenance activity cards for this equipment, to verify that the required storage main-

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tenance had been performed at the required frequencies.

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inspector concluded that the equipment supplier's storage re-

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quirements were being met.

The inspector also verified that the new storage facility compliea with the level B requirements as specified in ANSI N45.2.2. The specific attributes of ANSI N45.2.2 were inspected:

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precautions have been taken against vandalism

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items are placed on pallets or shoring to permit air cir-culation

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uniform heating and temperature controls have been provided

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floors are paved and well drained

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controlled access to storage areas has been provided

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cleanliness and good housekeeping practices are enforced

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fire protection has been provided and maintained

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rodent control has been provided No items of noncompliance were identified.

5.

Exit Interview The inspector met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on Februar, 1979.

s, The inspector summarized the purpose and scope of the inspection and the findings.

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'o UNITED STATES y*

NUCLEAR REGULATORY COMMISSION

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JUNE

7379 Docket tio. 50-321

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MEMORAfiDUM FOR:

T. A. Ippolito, Chief, ORS #3, D0R FROM:

D. M. Verrelli, Project Manager, ORB #3, DOR SUBJECT:

FORTHCOMING MEETING WITH GEORGIA POWER COMPANY Time & Date:

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June 13, 1979 Location:

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?-700 Purpose:

Discuss with Georgia Power Company, re102 application for Hatch Unit No. 1.

Specific items of discussion inc.lude E0C Recirculation Pump Trip and RPS Power Supply design and Technical Specifications.

Participants:

NRC J. T. Beard, D. Tondi, D. Verrelli, T. Ippolito, NRC Consultants, M. Mendonca GPC J. Bet ill, et a.

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CJ4'MQ Day d M. Verr lli, Project Manager Operating Rp ctors Branch #3 Division of Operating Reactors r-

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