ML20209H585
| ML20209H585 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/11/1986 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20209H563 | List: |
| References | |
| NUDOCS 8609150284 | |
| Download: ML20209H585 (2) | |
Text
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4 Art ws", 2 ADMINISTRATIVE CONTROLS
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Proposed tests and experiments which affect plant nuclear safety and i
c.
are not addressed in the Final Safety Analysis Report shall be l
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 violations of Technical Specifications shall be investigated and a report prepared which evaluates the event and which provides recommendations to prevent recurrence. Such report shall be approved by the Director, Nuclear Plant Operations and fomarded to the i
Chaiman of the Nuclear Safety Review Committee.
e.
Individuals responsible for reviews performed in accordance with i
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- 6. 5. 3.1. a. 6. 5. 3.1. b, 6. 5. 3.1. c and 6. 5. 3.1. d s ha l l be membe rs o f the plant staff that meet or exceed the qualification requirements of Section 4 of ANSI 18.1, 1971, as previour.ly designated by the
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Director, Nuclear Plant Operations. Each such review shall include a determination of whether or not additional, cross-disciplinary, i
review is necessary.
If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.
f.
Each review will include a determination of whether or not an I
unreviewed safety question is involved.
RECORDS 6.5.3.2 Reccrds nf the above activities shall be provided to the Director, Nuclear Plant Opc ations, PSRC and/or NSRC as necessary for required reviews.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS:
The Commission shall be notified and a report submitted pursuant a
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 6.7.1 The following actions shall be" taken in the event a Safety Limit is
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r violated:
The NRC Operations Center shall be notified by telephone as soon as a.
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
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be reviewed by the PSRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
TheSafetyLimitViolationReportshallbesubmittedtotheCommissio(
c.
the NSRC and the Vice President, Nuclear Operations within 14 days of the violation.
StMIER - UNIT 1 6-12 Amendment No. 8609150204 860911 PDR ADOCK 05000395 P
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ATTACHMENTil NO SIGNIFICANT HAZARDS DETERMINATION Based on the following evaluation, SCE&G has determined the proposed change does not involve a significant hazards consideration.
1.
Does the change involve a significant increase in the probability or consequences of an accident previously evaluated? No The proposed change is an administrative change which specifically states the requirements for those persons acting as qualified procedure reviewers at the i
j Virgil C. Summer Nuclear Station. The purpose of the change is to ensure that I
those persons performing in the capacity of a qualified procedure reviewer have adequate experience and training to perform the reviews. The revision is intended to be clarifying in nature and therefore will not increase the probability or consequences of an accident previously evaluated.
I 2.
Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? No The proposed change does not change the physical plant design and therefore does not create the possibif ty of a new or different kind of accident.
3.
Does the change involve a significant reduction in a margin of safety? No The proposed change is considered clarifying and administrative in nature.
Margins of safety are not impacted by the change.
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