ML20125B901
| ML20125B901 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/18/1972 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Dienhart A NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20125B881 | List: |
| References | |
| NUDOCS 9212100207 | |
| Download: ML20125B901 (3) | |
Text
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Northern States Power Co.
ATTN: Mr. Arthur V; Dienhart Vice President of Engineering _
414 Nicollet Mall' l
Minneapolis, Minnesota 55401 q
Gentlemen:
In June-1970 the-Atomic Energy Commission issued requirement 1 for -
quality. assurance for nuclear power plants.
Section 50.34(b)(6)(ii) and Appendix B of-10 CFR 59 set.forth the-criteria. for a. quality -
assurance program for design, construction 1and_ operation-off the structures,
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systems'and components of the' facility.
Your application for 'a full term license for~ the Monticello Nuclear-Generating Plant dated June 15, 1972, addressed.. in part, your quality assurance program'for. operations. _ Your submittal was evaluated against the criteria of Appendix' B as each applies to quality assurance during operation of the facility.
In particular, we were. interested in determining to what 4
extent your program covers such activities as operation, maintenance,l repair, refueling, and modification. -; Also reviewed was _the change-request ' dated-November 20,.1972 to the Monticello-license, which included a proposed:
Section 6, Administrative Centrols of the Technical' Specifications.
0ur -
- review disclosed some specific deficienciesJin. your program, which are.
tabulated below:
Criterion Items Not-Addressed _or Inadeouately Coveredi 0
I' A provision that those: checking,-auditing, Lor' inspecting haveL
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sufficient independence!of.the line organization responsib1'e for operation -
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i Cri terion_
ltems Not Addressed or inadequately Covered II Special controls processes, test equipment, tools, and skills to obtain and verify quality.
VI 1.
Procedures to cover review, approval, i.t:uance, and use of both initial and revised documents.
i 2.
Review and approval of document revisions by the same organization, that performed the original review and 1
approval.
XI 1.
Proof tests prior to installation, preoperational tests, e'
and operational tests.
2.
Test.esults documented and evaluated to assure that the test requirements have been satisfied.
XIV Measures to indicate the operating status of structures, systems, and components to prevent inadvertent operation.
XVI 1.
Measures to assure that the corrective action is sufficient to preclude recurrence of the unsafe operating condition.
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2.
Procedures to assure that the cause and corrective action are properly documented and reported..
XVII 1.
Records, such as operating logs, and results of reviews, 1
inspections, tests, and audits.
2.
Records which include such items as completed procedures and the qualifications of personnel.
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4 Criterion Items Not' Addressed or Inadequately Covered 3.
Inspection and test records which, as a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the actions taken on noted deficiences.
4.
Records which are identifiable and retrievable.
1.
5.
The duration of record retention, and their location and assigned responsibility.
As you may be aware, Safety Guide No. 33, Quality Assurance Program Requirements (Operation), was issued on November 3,1972.
The Guide references ANS 3.2, Standard for Administrative Controls for Nuclear-Power Plants, and ANSI N45.2-1971, quality Assurance Program Requirements for Nuclear Power Plants.
Conformanca with these standards will provide an adequate basis for complying with J.ppendix B of 10 CFR Part 50.
Please reassess your quality assurance program as it applies to the operations phase of plant life, in light of Safety Guide No. 33 and the above comments, and resubmit within 90 days, a Cescription of the program that is responsive to the guide.
Where reference is made in the discussion
' that the requirement is satisfied by a statement in the Technical Specifi-cations, a specific reference to-the appropriate subsection of the Technical Specifications should be made.
To assist you in preparing your reply we have enclosed a copy of Safety Guide No. 33.
Sincerely, a
Donald J. Skovholt, Assistant' Director
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Enclosure:
for Operating Reactors Safety Guide No. 33 Directorate of Licensing
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