ML20205M442

Proposed Tech Specs,Section 6,pp 6-5,6-8 & 6-13

ML20205M442
Person / Time
Site:	Vogtle
Issue date:	10/25/1988
From:	GEORGIA POWER CO.
To:
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ML20205M441	List: ML20205M436 ML20205M442
References
NUDOCS 8811030097
Download: ML20205M442 (4)

Text

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ENCLOSURE 3 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS SECTION 6 REFERENCES INSTRUCTIONS FOR' INCORPORATION The proposed change to the Technical Specifications (Appendix A to Operating License NPF-68) would be incorporated as follows:

Remove Page Insert Page 6-5/6-6 6-5*/6-6 6-7/6-8 6-7/6-8*

6-13/6-14 6-13*/6-14

• page on which the revision has been made.

VL-99 E3-1 10/25/88 0067e

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TA8LE 6.2-1 MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, or 4 M00E 5 or 6 05 1 1 SRO 1 None R0 2 1 NLO 2 1 STA 18 None 05 -

Operations Supervisor with a Senior Operator license on Unit 1 SRO -

Individual with a Senior Operator license on Unit 1 RO -

Individual with an Operator license on Unit I N'.0 -

Non-Licensed Operator STA -

Shift Technical Advisor The shift crew composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to 6.Neeed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of o -duty shift crew pencer: pre.id;4 immediate action is taken to restore the sh ft crew composition to within the minimum requirements of Table 6.2-1. This p ovision does not permit any shift crew position to be unmannad upon shift ch ,ge due to an oncoming shi ' crewman being late or absent.

During any absence of the Operations Supervisor from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the control room command function.

During any absence of the Operations Supervisor from the control room while the unit is in MODE 1 or 6, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

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• The STA position shall be manned in MODES 1, 2, 3, and 4 unless the Operations Supervisor or the individual with a Senior Operator license meets the qualifications for the STA as required-by-the-MRC# .3 A hd in /4c Ak/

.Sh rcment en Jojincennf fywhe nr .5&ft , ahkc/ Q:&/xt M, MfL V0GTLE - UNIT 1 6-5

• )

l ADMINISTRATIVE CONTROLS -

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RESPONSIBILITIES (Continued)  !

b. Review of 1) programs required by Specification 6.7.4 and changes thereto, and 2) proposed procedures and changes to procedures which involve an unreviewed safety question as per 10 CFR 50.59.

c. Review of all proposed tests and experiments that affer,t nuclear safety;

d. Review of all proposed changes to the Technical Specifications;

e. Review of all proposed changes or mod ications to plant s tems or equipment that affect nuclear safet d c5 To ind 4 d Mf / "/ Cec /

C/npfe /4.3 of the Vey/k Pn/ St4 darfysis 4,9Avi  ;

f. Investigation of all violations of he Technical Specifications, including the preparation and forwarding of rept s covering evalua-tion and recommendations to prevent recurrence, so the Vice President - Nuclear and to the Safety Review Board;

g. Review of all REPORTABLE EVENTS;

h. Review of plant operations to detect potential hazards to nuclear safety;

i. Performance of special reviews, investigations, or analysel and reports thereon as requested by the General Manager - Nuclear Plant l or the Safety Review Board;

j. Review of the Security Plan and implementing procedures and submittal of recommended changes to the General Manager - Nuclear Plant and the Safety Review Board;

k. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the General Manager - Nuclear Plant and the Safety Review Board;

1. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President -

Nuclear and to the Safety Review Board;

m. Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE OOSE CALCULATION MANUAL, and the Radwaste Treatment Systems; and

n. Review of the Fire Protection Program and Implementing procedures and submittal of recommended changes to the General Mnager - Nuclear Plant.

6.4.1.7 The PR8 shall:

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a. Recommend in writing to the General Manager - Nuclear Plant approval or disapproval of items considered unoer Specification 6.4.1.6a. l through e. prior to their implementation; V0GTLE - UNIT 1 6-8 Amendment No. 6

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m ADMINISTRATIVE CONTROLS 6.6 SAFETY LIMIT VIOLATION

6.6.1 violated

The following actions shall be taken in the event a Safety Limit is a.

In accordance with 10 CFR 50.72, the NRC Operations Center shall be notified by telephone as soon as practical and in all cases within one hour after the violation has been determined. The Vice President - Nuclear, the SR8, PRB, and the General Manager - Nuclear Plant 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 Licensee Event Report shall be prepared in accordance with 10 CFR 50.73.

c.

The Licensee Event Report shall be submittad to the Commission in accordance with 10 CFR 50.73, and to the PRB, SR8, the General Manager - Nuclear Plant and the Vice President - Nuclear within 30 days after discovery of the event.

d.

Critical operati0n of the unit shall not be resumed until authorized by the Nuclear Regulatory Commission.

6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.

The emergency cperating procedures required to implement the require-ments of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic letter No. 82-33;

c. Security Plan implementation;

d. Emergency Plan implementation;

e. PROCESS CONTROL PROGRAM implementation; f.

OFFSITE DOSE CALCULATION MANUAL implementation; g.

Quality Assurance for effluent and environmental monitoring;

h. Fire Protection Program Implementation; and

i. Technical Specifications Improvement Program implementation /

(f&1K Oppier N..$).

6.7.2 Each procedure of 6.7.1 above, and changes thereto, shall be reviewed as set forth in administrative procedures and approved by either the General Manager - Nuclear Plant or the department head of the responsible dspartment prior to implementation with the exception of the following which shall be approved by the General Manager - Nuclear Plant:

l V0GTLE - UNIT 1 6-13 Amendment No. 6