ML19338D099

Proposed Changes to Tech Specs Tables 3.2-11,4.2-11 & 6.2.2-1 & Tech Specs 6.3 for Unit Staff qualifications,6.4 for Training & 6.5 for Review & Audit

ML19338D099
Person / Time
Site:	Hatch
Issue date:	09/15/1980
From:	GEORGIA POWER CO.
To:
Shared Package
ML19338D095	List: ML19338D094 ML19338D099 ML19338D103
References
NUDOCS 8009190428
Download: ML19338D099 (6)

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ATTACIDIENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN 1. liATCll NUCLEAR PLANT UNIT 1 PROPOSED CliANCES TO TECIINICAL SPECIFICATIONS The proposed changes to the Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Remove Pages Insert Pages 3.2-22 3.2-22 3.2-23 3.2-23 3.2-48 3.2-48 6-4 6-4 6-6 6-6 8000100

Table 3.2-11 INSTRUMENTATION WHICH PROVIDES SURVEILLANCE INFORMATION Required m Ref. Operable No. Instrument Instrument Type and

{j r (a) (b) Channels Range Action Remarks 5

a 1 Reactor Water Level (CE/MAC) 1 Recorder (c) (d)

@ 2 Indicator 0 to 60" (c) (d)

E 2 Shroud Water Level 1 Recorder (c) (d) s d 1 Indicator +200" to +500" (c) (d) 3 Reactor Pressure 1 Recorder (c) (d) 2 Indicator 0 to 1200 psig (c) (d)

4. Drywell Pressure 2 Recorder -5 to +80 psig (c) (d) 5 Drywell Temperature 2 Recorder 0 to 500 F (c) (d) 6 Suppression Chamber Air Temperature 2 Recorder 0 to 500oF (c) (d) 7 Suppression Chamber Water Temperature 2 Recorder 0 to 2500F (c) (d) u k' 8 Suppression Chamber Water Level 2 Indicator 0 to 300" (c) (d)

U 2 Recorder 0 to 30" (c)(e) (d) 9 Suppression Chamber Pressure 2 Recorder -5 to +80 psig (c) (d) 10 Rod Position Information System (RPIS) 1 28 Volt Indicating Lights (c) (d) 11 Hydrogen and Oxygen Analyzer 1 Recorder 0 to 52 (c) (d) 12 Post LOCA Radiation Monitoring System 1 Recorder (c) (d)

Indicator 1 to 106 R/hr (c) (d) 13 Drywell/ Suppression Chamber Differential Presusre 2 Recorder -0.5 to +2.3 psid (c) (e) (d) 14 a) Safety / Relief Valve Position Primary 1 Pressure Switch 4-100 psig (f)

Indicator b) Safety / Relief Valve Position Secondary 1 Temperature element 0-600 F (f)

Indicator

NOTES FOR TABLE 3.2-11

a. The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can m be establsihed between items in Table 3.2-11 and items in Table 4.2-11.

H b. Limiting Conditions for Operation for the Neutron Monitoring System are listed in Table 3.2-7.

c. From and after the date that one of these parameters is reduced to one indication, continued 9 operation is permissible during the succeeding thirty days unless such instrumentation is sooner g made operable.

N Continued operation is permissible for seven days from and after the date that one of these g

parameters is not indicated in the control room. Surveillance of local panels will be substituted for indication in the control room during the seven days.

d. Drywell and Suppression Chamber Pressure are each recorded on the same recorders. Each output channel has its own recorder.

Drywell and Suppression Chamber air temperature and suppression chamber water temperature are all recorded on the same recorders. Each output channel has its own recorder. Each recorder y takes input from several temperature elements.

Y g Hydrogen and Oxygen are indicated on one recorder. The recorder has two pens, one pen for each parameter.

Each channel of the post LOCA radiation monitoring system includes two detectors; one located in the drywell and the other in the suppression chamber. Each detector feeds a signal to a separate log count rate meter. The meter output goes to a two pen recorder. One high radiation level alarm is provided per channel and annuciation of alarm is provided in the control room.

e. In the event that all indications of this parameter is disabled and such indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours.and a Cold Shutdown condition i? the following eighteen (18) hours.

f. 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 increase which might be indicative of an open SRV. With both the prinary and secondary monitoring channels of two or more SRVs inoperable 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 />.

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Table 4.2-11 .

Check and Calibration Minimum Frequency for Instrumentation

.o Which Provides Surveillance Information ,

Ref. Instrument Instrument. Check Instrument Calibration

- No. Minimum Frequency Minimum Frequency h (a) (b) (c)

O E

s 1 Reactor Water Level Each shift Every 6 months d

(GE/MAC) w 2 Shroud Water Level Each shift Every 6 months ,

3 Reactor Pressure Each shift Every 6 months 4 Drywell Pressure Each shift Every 6 months 5 Drywell Temperature Each shift Every 6 months 6 Suppression Chamber Air Each shift Every 6 months Temperature F 7 Suppression Chamber Water Each shift Every 6 months Y

Temperature co 8 Suppression Chamber Water Each shift Every 6 months Level 9 Suppression Chamber Each shift Every 6 months Pressure 10 Rod Position Information Each shift N/A System (RPIS) 11 Hydrogen and Oxygen Each shift Every 6 months Analyzer 12 Post LOCA Radiation Each shift Every 6 months 13 Dry'. 1/ Suppression Chamber Each shift Every 6 months DifDr, cial Pressure Every 18 months 14 a) Saf o, e- lief Valve Position Pri- Monthly mary Inui.cator Monthly Every 18 months b) Safety / Relief Valve Position Secondary Indicator

TABLE 602.2-1 MINDIUM SHIFT CREW COMP 05ITION#

Condition of Unit 1 - Unit 2 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 Shitt Technical Advisor ## 1 1 Condition of Unit 1 - Unit 2 in Cold Shutdowr Condition or Refuel Mode LICENSE AP?LICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL ** 2 1*

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

OL 2 1 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.

• • Assumes each individual is licensed on both units.

1. Shift crew composition, including an individual qualified in radiation I 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. Effective January 1, 1981. '

PlddiT HATCH UNIT 1 6-4 1

b

ADMINISTRATIVE CONTROLS 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 Health Physicist-Radiochemist who shall meet or exceed the qualifications of 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 with specific training in plant desiga, and response and analysis of the plant 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 of 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 Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for fire protection shall be maintained under the direction of the Senior Reg >21atory Specialist and shall meet or 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.

COMPOSITION 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 in PRB activities at any one time.

PLANT HATCH UNIT 1 6-6