ML20133F962

Proposed Changes to Tech Spec 6.5.3.1(e),authorizing Individuals Designated by Director of Plant Operations as Qualified Procedure Reviewers.No Significant Hazards Determination Encl

ML20133F962
Person / Time
Site:	Summer
Issue date:	08/02/1985
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20133F953	List: ML20133F950 ML20133F962
References
NUDOCS 8508080505
Download: ML20133F962 (3)

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ADMINISTRATIVE CONTROLS

c. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report shall be

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reviewed by an individual / group other than the individual / group which prepared the proposed test or experiment.

d. Events reportable pursuant to the Technical Specification 6.9 and l violations of Technical Specifications shall be investigated and /

a report prepared which evaluates the event and which provides F recommendations to prevent recurrence. Such report shall be approved by the Director, Nuclear Plant Operations and forwarded to the Chairman of the Nuclear Safety Review Committee,

e. Individe:1 respencible fer revie"r perfe red in :::;rd:n:: afth

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0. 5. 3.1. E , S. 5. 3.1. b , S. 5. 3.1. : :nd S. 5. 3.1. d s hell 1,. ....../, r= v f \

e the pl:nt :t:ff that :::t er eNeced th- a"*inti rz;ir m at:

Imed.b,9 . er section 4.4 ef t,Z: 10.1, 1^71, ;; previ;;:.ly J..ir mi.ed by i/n.

Directer, Mer!: r Plant Operetiens-Eech 5"c5 r: vira :h:11 include e deter;;;ination of ab;ther er net additienel, cr;;;-di;;iplin ry, revira 1: n;:::::ry. If d:: :d neteese y 5"th revira shell be pee W = d by the revir? ?:r: Enc! Of the !??r;priete disciplinw.

f. Each review will include a determination of whether or not an unreviewed safety question is involved.

RECORDS 6.5.3.2 Records of the above activities shall be provided to the Director, Nuclear Plant Opt. ations, PSRC and/or NSRC as necessary for required reviews.

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6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the PSRC and the results of this review shall be submitted to the NSRC and the Vice President, Nuclear Operations.

! 6.7 SAFETY LIMIT VIOLATION I

6.7.1 The following actions shall be taken in the event a Safety Limit is violated: ( '

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a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President, Nuclear Operations and the NSRC shall'be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

! b. A Safety Limit Violation Report shall be prepared. The report shall l be reviewed by the PSRC. This report shall describe (1) applicable ( '

circumstances preceding the violation, (2) effects of the violation j upon facility components, systems or structures, and (3) corrective '

action taken to prevent recurrence.

c.

i TheSafetyLimitViolationReportshallbesubmittedtotheCommission,(

the NSRC and the Vica President, Nuclear Operations within 14 days of the violation. 8508080505 DR e50002 ADOCK 05000395 PDR SUPMER - UNIT 1 6-12 Amendment No. 35 i,

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. -s INSERT "A"

e. Individuals responsible for reviens performed in accordance with 6.5.3.1(a),

6.5.3.1(b), 6.5.3.1(c), and 6.5.3.1(d) shall have a minimum of four (4) years experience, at least two of which is in .the nuclear field. One (1) year may be fulfilled through academic or related technical training. Designation as a qualified reviewer must be approved by the Director, Nuclear Plant Operations.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.

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• o ATTACHMENT 2 Proposed "No Significant Hazards Determination" Technical Specification 6.5.3.1(e) defines the qualification requirements for individuals responsible for performing reviews required by Specifications 6.5.3.l(a) thru (d). Current Technical Specification requirements have been determined to be inadequate in that they do not specifically state the requirements for all the individuals at the plant designated as qualified reviewers by the Director, Nuclear Plant Operation. The proposed change would correctly identify and establish consistent qualification requirements for plant l personnel tasked with performing reviews required by the Technical Specifications.

SCE&G therefore considers the change to be administrative in nature and has determined that issuance of an amendment will not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated;

2) create the possibility of a new or different kind of accident from any accident previously evaluated; 3) involve a significant reduction in a margin of s a fe t y.

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