ML20128F425
| ML20128F425 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Prairie Island  |
| Issue date: | 03/10/1977 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9212080331 | |
| Download: ML20128F425 (5) | |
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LICENSEE:
Northern States Power Company FACILITIES: Monticello Nuclear Generating Plant Prairie Island Nuclear Generating Plant Unit Nos.1 and 2 f
SUMMARY
OFMEETINGWITHNORTHERNSTATESPOWERCOMPANY(NSP)REGARDING 1
PROPOSED QUALITY ASSURANCE PROGRAMS FOR MONTICELLO AND PRAIRIE ISLAND (UNIT NOS. 1 AND 2) NUCLEAR GENERATING PLANT On Tuesday, March 1,1977, representatives of the NRC staff and NSP met to discuss the QA Program description submitted on September 30, i
1976. The attendance list is given in attachment 1.
The agenda for the meeting is given in attachment 2.
The agenda items were discussed thoroughly and the questions were satisfactorily answered. We concluded that a request for additional infomation would not have to be issued; however, based on our discussion, NSP will submit some clarifying changes in the program.
NSP will comit to ANSI N18.7; however, some interpretations of the relationship between AHSI N18.7 and the related regulatory guides by the staff will require NSP to reword their comitment to ANSI _N18.7.
Other than the above, the NSP QA Program is generally satisfactory and we expect to be able to issue a letter indicating that the program is adequate upon receipt of the clarifying infomation discussed at this meeting.
Marshall-Grotenhuis, Project Ha11ager Operating Reactors Branch #2 Division of Operating Reactors Attachments:
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Attendance List 2.
Agenda
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NORT1ERN STAT.E$ POWER COMPANY J"
Northern States Power Company i
L. Mayer F. Tierney, Jr.
R. Scheinost T. McFadden J. Leveille NRC - Staff M. Grotenhuis R. Snaider N. Choules J. Gilray C. lleitemes W. Belle 1
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. (a Discuss your comitnent to comply with tie controls referenced or contained in ANSI N18.7 - 1976 " Administrative Controls and 1.
Quality Assurance for the Operational Phase of Nuclear P 1
1.74,1.88 - Rev.1, and:1.94 1.39, 1.54, 1.58, 1.64 - Rev.dau,gher standards referenced in l
which endorse the ANSI N45.2 ANSI !!18.7 - 1976.
Discuss the QA controls that apply to the Engineering & Construction Provide
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and the Transmission and Operations Services organizations.
2.
a clear description of the QA Program controls that ap of itonticello and Prairie Island.
"In general, assurance of quality Discuss the following statement:
requires management measures which provide that the ir.dividual or 3.
group assigned the responsibility for checking, auditing, inspecting, or othernise verifying that an activity has been correctly perfomed is independent of the individual or group directly responsible for The use of the words "In performing the specific activity." general" does not provide us wi degree to which you will comply with this control.
Discuss the authority and independence of the Gene 4
0f?the QA program.
establishing andlessurih@'impfehent5 tion Describe the lines of comunication, quality assurance authority, and implementation of the operational QA Program in tems of the S.
quality affecting activities perfomed by the Manager of Fuel Procurement; Manager of Nuclear Support Services; Plant Engineering and Construction (PEC) General !!anager and PEC QA tianager: Transm i
and Operations Services (TOS) General Manager of Maintenance & Test ng and TOS Director of Services.
Describe in more detail how disputes involving qualit 6.
identified in 5, includinguthosetdepartments'underatherGeneralneral Manager of Power Producticn, are resolved.
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Section 3.I6'.1 specifies tht the Quality Engineer. reports a&ninistratively to the Superintendent of Plant Engineering
& Radiation Protection. Desctibe who the Quality Engineer reports to technically.
8.
Identify the safety-related structures, systems and components j
controlled by the QA Program er clearly describe the bases for determining what items fall urider the QA Program control (e.g.,
Regulatory Guide 1.26,1.29).
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Form AEC-318 (Ro. 9 53) AECM 0240 W u. s, oow a==u sa r Pan = Ytae o"'c as e e r..ea s ee e
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MEETING
SUMMARY
DISTRIBUTION j
i Docket NRC PDR Local PDR OP3 #2 Reading NRR Reading B. C. Rusche E. G. Case V. Stello K. R. Goller D. Eisenhut T. J. Carter A. Schwencer G. Lear R. Re.A W. Butler B. Grimes R. Baer L. Shao Project Manager - RPSnaider/MGrotenhuis Attorney, OELD - Stewis/ Riddle /Grainey/Silberstein 01&E (3)
R. Diggs NRC Participants (Major)
NChoules/JGilray/CHeltemes/WBelke R. Fraley, ACRS (16)
T. B. Abernathy, DTIE J. B. Buchanan Licensee t
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