ML19338D103

Proposed Changes to Tech Specs Tables 3.3.6.4-1,4.3.6.4-1 & 6.2.2-1 & Tech Specs 6.3 for Unit Staff qualifications,6.4 for Training & 6.5 for Review & Audit

ML19338D103
Person / Time
Site:	Hatch
Issue date:	09/15/1980
From:	GEORGIA POWER CO.
To:
Shared Package
ML19338D095	List: ML19338D094 ML19338D099 ML19338D103
References
NUDOCS 8009190432
Download: ML19338D103 (5)

Text

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ATTACHMENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS The proposed changes to the Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Pages Insert Pages 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 6-4 6-4 6-5 6-5 l

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8009190 fh 932-

TABLE 3.3.6.4-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM 2 CHANNELS INSTRUMENT OPERABLE 9 2

1. Reactor Vessel Pressure (2C32-R605 A, B, C)

E E 2. Reactor Vessel Water Level (2B21-R610, 2B21-R615) 2 w

3. Suppression Chamber Water Level (2T48-R622 A, B) 2

4. Suppression Chambar Water Temperature (2T47-R626, 2T47-R627) 2

5. Suppression Chamber Pressure (2T48-R608,2T48-R609) 2

6. Drywell Pressure (2T48-R608, 2T48-R609) 2

7. Drywell Temperature (2T47-R626, 2T47-R627) 2 y 8. Post-LOCA Gamma Radiation (2Dll-K622 A, B, C, D) 2

9. Drywell H 2

-0 2 An lyzer (2P33-R601 A, B) 2

10. a) Safety / Relief valve Position Primary Indicator (2B21-N301 A-H and K-M)

• b) Safety / Relief Valve Position Secondary Indicator (2B21-N004 A-H and K-M) *

• If either the primary or secondary indication is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increases which might be indicative of an open SRV. With both the primary and secondary monitoring channels of two or more SRVs inoperabic either restore sufficient inoperable channels such that no more than one SRV has both primary and secondary channels inoperable within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

" TABLE 4.3.6.4-1

~ POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Y

CHANNEL CHANNEL h

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CHECK CALIBRATION INSTRUMENT O

O 1. Reactor Vessel Pressure M Q N

2. Reactor Vessel Water Level M Q

3. Suppression Chamber Water Level M R

4. Suppression Chamber Water Temperature M R

5. Suppression Chamber Pressure M R

{ 6. Drywell Pressure M Q

7. Drywell Temperature M R

8. Post-LOCA Gamma Radiation M R

9. Drywell H2 -02 Analyzer M Q

10. a) Safety / Relief Valve Position Primary Indication M* R b) Safety / Relief Valve Position Secondary Indication M* R

• See 4.4.2.a

TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION #

Condition of Unit 2 - Unit 1 in Reactor Power Operation, Hot Standby or Hot Shutdown Condition LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL ** 2 2*

OL** 3 2 Non-Licensed 3 3 Shif t Technical Advisor ## 1 1 Condition of Unit 2 - Unit 1 in Cold Shutdown Condition or Refuel Mode LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SQL** 2 1*

OL** 2 2 Non-Licensed 3 3 Shift Technical Advisor ## 1 None l

Condition of Unit 2 - No Fuel in Unit i LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1 1* l 2 1 I OL Non-Licensed 2 1 Shift Technical Advisor ## 1 None

• Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervisoring CORE ALTERATIONS.

• • Ass'umes each individual is licensed on both units.

1. Shift crew composition, including an individual qualified in radiation Protection procedures, may be less than the minimum requirements for a period of time not to exceed 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 on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.2-1.

1. 1. Ef fective January 1,1981.

PLANT HATCH UNIT 2 6-4

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ADMINISTRATIVE C0iiTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the llealth Physicist-Radiochemist who shall meet or exceed the qualifications cf Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline tith specific training in plant design, and response and analysis of the plart for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction cf the Senior Methods and Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appenlix "A" of 10 CFR Part 55.

6.4.2 A training program for fire protection shall be maintained under the direction of the Senior Regulatory Specialist and shall meet er exceed the requirements of Section 27 of the NFPA Code-1975, except for fire protection training sessions which shall be held at least once per 92 days.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

FUNCTION 6.5.1.1 The PRB shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSlTION 6.5.1.2 The Plant Review Board shall be composed of the:

Chairman: Plant Manager Vice Chairman: Assistant Plant Manager Member: Operations Superintendent Member: Superintendent Plant Engineer Services Member: Maintenance Superintendent Member: Senior Quality Control Specialist Member: Health Physicist-Radiochemist ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members iri PRB activities at any one time.

l PLANT HATCH UNIT 2 6-5 I

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