ML19225C254

Revised Tech Specs Re Surveillance Requirements for Diesel Generator & Channel Calibr Following Seismic Event & Max Permissible Level Numbers of Seismic Monitoring Instruments in Table 3.3.6.2-1

ML19225C254
Person / Time
Site:	Hatch
Issue date:	07/19/1979
From:	GEORGIA POWER CO.
To:
Shared Package
ML19225C251	List: ML19225C250 ML19225C254
References
NUDOCS 7907260751
Download: ML19225C254 (4)

Text

e ATTACll'4ENT 1 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDUIN I. IIATCll NUCLEAR PLANT l"IIT 2 PROPOSED CIIANCES TO TECll'?ICAL SPECIFICATIONS _

Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License NPF-5 and have determined that:

.a)

The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)

The proposed anendment does not contain several complex issues, does not involve ACRS review, or does'not require an environmental impact statement; c)

The proposed amendment does not involve a complex issue, an environ-mental issue or more than one safety issue; d)

The proposed amendment is editorial and administrative in nature; namely:

(1) The correction of an inadvertent substitution of a load rating in units of horsepower for units of kilowatts; (2)

The changing of two !@L numbers which were printed incorrectly in a table; (3) An administrative change which will extend the required time for a channel calibration following a seismic event from 5 to 30 days;.and d)

The proposed amendment is therefore a Class II amendment.

gq o k, p'q s t t

454 232

ATTACllMENT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. IIATCll NUCLEAR PLANT UNIT 2 PROPOSED CllANGES TO TECllNICAL SPECIFICATI0';S The proposed changes to the Technical Specifications (Appendix A to Opera'ing License NPF-5) would be incorporated as follows:

Remove Pane Insert Page 3/4 8-3 3/4 8-3 3/4 3-48 3/4 3-48 3/4 3-47 3/4 3-47 l

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i a n o p eo "$ 5 5 -r :jf

ELECTRICAL POWER SYSTEMS SURVE!LLANCE REQUIREMENTS (Continued) 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 4.8.1.1.2-1 on a STAGGERED TEST BASIS by:

1.

Verifyirg the fuel level in the day fuel tanks.

2.

Verifying the fuel level in the plant fuel storage tank.

I 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel starts from ambient condition and accelerates to synchronous speed in 5 12 seconds.

5.

Verifying tho generator is synchronized, loaded to 2764 kw for diesel generator 2A, 2360 kw for diesel generator 1P or 2742 kw for diesel generator 2L in 5 120 seconds, and operates for > 60 minutes.

6.

Verifying the diesel generator is aligned to provide itandby power to the associated emergency busses.

7.

Verifying the pressure in bo;.1 diesel air start receivers to be > 225 psig.

b.

At least once per 92 days by verifying that a sample of aiesal fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment.

c.

At least once per 18 months during shutdown by:

1.

Subjecting the diesel to an inspection in accordance witr procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2.

Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within i 10% of its design interval.

3.

Verifying the generator capability to reject a load of

> 798 kw while maintaining voltage at 4160 1 400 volts and frequency at 60 1 2 Hz.

454 234 HATCH

'JNIT 2 3/4 8-3

TABLE 3.3.6.2-1

_ SEISMIC M0flITORIf1G If1STRUMEf1TATI0ft MIf11 MUM MEASUREMEf1T If4STRUMEfiTS If1STRUMEtiTS Af1D SEllSOR LOCATIOH RAfGE OPERABLE Triaxial Time-History Accelerographs( ) IC) 1.

a.

Diesel Generator Building El 130'0" 0-0.5g 1

(2L51-tiO21) b.

Reactor Building 87' Level on Drywell Pedestal (2L51-f;020) 0-0.59 1

c.

Drywell - Feedwater Inlet to RPV 0-0.5g 1

2L51-fl004 Switchyard (c) (lL51-fl00r) d.

0-0.5g 1

2.

Triaxial Peak Recording Accelerometers a.

Diesel Generator Base Support (c) 0-1.09 1

(l L51-f1007) b.

Intak? Structure (c) (lL51-f;006) 0-1.0g 1

c.

Contr]l B.uilding Main Control Roor Floor (c) (l L51-f;008) 0-1.0g 1

d.

Control Building Floor El 112'(c) 0-1.0g 1

(2L51-fl028) e.

Reactor Bldg Refueling Floor 0-1.09 1

(2L51-f;029) f.

Reactor Pedestal Inside Biological Shield (2L51-fl035) 0-2.0g 1

g.

Reactor Piping - Feedwater Inlet to RPV (2L51-f;034) 0-2.0g 1

3.

Triaxial Seismic Switches (b) a.

Reactor Building 87' Level on Drywell Pedestal (2L51-fl022) 0.025-0.25g 1

b.

Reactor Building 185' Level Out-side Biological Shield (2L51-f;024) 0.025-0.25g 1

4.

Triaxial Response Spectrum Recorder (d) llakh - Unit 1 Cont)ainment a.

2-26 llz 1

Found tion El 87.(c

( L51-fl105) 0-0.5g UWith main control room indicatio., and annunciation.

bWith main control room annunciatior.

cShared with Hatch - Unit 1.

b ifATCH - Uf1IT 2 3/4 3-48

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.2 The seismic monitoring instrumentation shown in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITt. At all times.

ACTIO!!:

a.

With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, in lieu,f any other report required by Spet.ification 6.9.1, prepare and submit a Special Report to the Commission within the next 10 days outlining the cause of t1e malfunegion and the plans ;or restoring the instrument's) to OPERABLi etatus.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.6.2.1 Each of the above required seismic monitoring instruments shall be demonstrated 0?ERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEET and CHANNEL CALIBRATION operations at the frequencies shown

\\

in Table 4.3.6.2-1.

4.3.6.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 30 days follcwing the l

seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

In lieu of any other report required by Specification 6.9.1, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

454

,C,6 HATCH - UNIT 2 3/4 3-47