ML20127N549

Submits Comments Based on Review of 691121 Draft TS Submittal & Amend 23

ML20127N549
Person / Time
Site:	Monticello
Issue date:	12/04/1969
From:	Brauner A US ATOMIC ENERGY COMMISSION (AEC)
To:	Vassello D US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212010306
Download: ML20127N549 (3)

Text

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D. Vassallo, Reactor Projects Branch $

Division of Reactor Licensin8 OHrinni Fred tv THRU Ndley Thompson, Q11ef Decm, n o, s3n Operational Safety Branch, DRL REVIEW OF N3tTHERN WATES POWER COMPANY'S (Morf1 CELLO DOGCET NO. 50 263)

K AMENDurt NO. 23, ' REVISED TEQINICAL SPECIFICATIONS," DATED 11/21/69 s

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The following coments are in reference to our discussion regardin6 tho Technical Specification draft autanittal of 10/20/69 and A:nendment No. 23 Section 1.0 - Definitions A.1 should be changed to read Results in any actual safety system setting less conservative than speci.

fled in the Limiting Safety System Bettings section of the Technical Specifications.

Section 6.0 - Administrative Controla 6.1.d Note: Ae Experience The third paragraph stites that intensive nuclear training sney be substi.

tuted for two-thirds of the required nuclear experience on the basis of one months training being equivalent to three months experience. To be consistent with the prvposed American helet.r Society 8tandard (ANS 3),

intensive training should only be substituted for a maximam of one year of the required nuclear experience rather than for two-thirds.

6.1.E.1.a The technical expertise requirements of the Safety Audit Committee and Consultants have been modified by the ap

However, some of the specialties listed in the 10/plicant as requested.20/69 submittal have be in the revised draft. Experience in nuclear power plant operation, reac.

tor physics, radiation damage and any other appropriate fields applicable to the Monticello plant abould be included as support in this area.

9212010306 691204 PDR ADOCK 05000263 l-A PDR l

i D. Yassallo 0[c 4 13E9 6.1.E.1.h Although it is not an abooluto necessity, it is desir. ole that the astety Audit Committee meet at least quartarly rather than twice yearly.

6.1.E.1.d.4 Tbic review should be expanded to include changes to the license, Techni-cal Dpecifications and the Safety Analysis Report unless this subject is covered by 6.1.E.1.d.6.

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6.1.E.1.d.$

Authorisation for resumption of operations vben a safety limit is exceeded does not include the AEC. Sinn the applicant is subject to this require-ment according to Section $0 36(c)(1)(1) of the Regulations, it la not mandatory that this notification be included in this paragraph, but for consistency it would be appropriate. On the other hand, the second sentence of this paragraph could be deleted entirely since it is covered under section 6.4 of the Technical Specifications.

6.1.E.1.d.6

' Itis review should be expanded to include changes to the license, TecLaical Specifications and the safety Analysis Report.

6.1.E.2.d.2

" Proposed changes to the Befety Analysis Reporc" should be included in the review by the Operations Committee, and they should also be submitted to the Safety Audit Cbaaittee for review.

Section 6.4 Authorisation by the AEC abould be included in this paragraph as suggested in 6.1.E.1.d.f.

An attempt ves made in the five preceding comments to clarify responsibil.

ity for review by the Operations and Safety Audit Comaittees. Beesuse interpretation is vague, it la suggested that this subject be discussed with the applicant in order to reach an understanding.

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_Section 6.6. Plant Reporting Requiremonte The Routine Opersting Reports section abould be revised to incorporate the i

requirements of the IRL Operational astety Guide No. 4 (draft $10). This revision pertains to the liquid, gaseous and solid radioactive effluent releases, environmental monitoring and thermal effects.

Ip/A. R. Brauner Operational Safety Branch, DRL ce!

D. J. Skovbolt, AD/EO, DRL D. Maller, mief, EFBfl, IRL b

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