ML20004F685

Application to Amend License NPF-9,consisting of Proposed Changes to Tech Specs 3/4.8.1,3/4.3.3.7 & Table 3.3-11 Re Fire Detection Instrumentation

ML20004F685
Person / Time
Site:	McGuire
Issue date:	06/17/1981
From:	Parker W DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20004F686	List: ML20004F685 ML20004F689
References
TAC-46812, NUDOCS 8106220180
Download: ML20004F685 (5)

Text

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• l 34 DUKE POWER CO>IPANY Powta Duzz.o No

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'/ CF P%ttscrwt TELEPaONE AmrA 7C4 s eu- e.vooceo- June 17, 1981 273-4osa Mr. Harold R. Denton,~ Director

-Office of Nuclear Reactor Regulation # D Nuclear Regulatory Commission hSh$l.(hf- 4

'U.S.

Washington,-D.-C. -20555 g'> V Q f'/ . g Attention: -Ms. E. G. Adensam, Chief- ,/;

Licensing Branch No. 4 - g.jg y 0 I93l A ,L~.

Re: McGuire Nuclear Station, Unit 1 R. " *Q Q us (9)

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Docket No. 50-369 s gj/

Dear Mr. Denton:

m rA-Attached are proposed changes to the McGuire Nuclear Station, Unit 1, Technical Specifications. These changes include the following itemc:

~ 1. ~ Exemption request from certain diesel generator testing require-ments.

2. Correction to listing of fire detection instrumentation.

Each of these items has been reviewed and it has been determined that there are no' adverse safety or environmental impacts associated with the proposed changes.

Verg truly yours,

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William O. Parker, Jr.

GAC:pw Attachment cc: Ms. M. J. Graham Mr. James P. O'Reilly, Director

-Resident Inspector U.S. Nuclear Regulatory Commission

.McGuire Nuclear Station Region II P

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Mr. Harold R.-Denton, Director

- June 17,11981 r- , Page Two WILLIAM 0.' PARKER, JR., being duly sworn, states that.he is Vice-President.of Duke Power Company; that he is. authorized on the part of'said Company.to sign and file _sith the Nuclear Regulatory Commission this revision to the McGuire Nuclear Station Technical Specifications, Appendix A to License No. NPF-9; and that all statements and matters set forth therein are-true and correct to the best of his knowl dge, i

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' William-0. Parker, Jr., Vic)t President Subscribed and sworn to before me this 17th day of June, 1981 ,

$ LJ- h No'tary Public

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.>f McGUIRE NUCLEAR STATION

. Technical Specification 3/4.8.1 A.C. Sources .

-Requested Action Duke Power Company hereby requests an exemption.from one of the requirements in Specification 4.8.1.1.2.d a. Specifically, an exemption is requested from

-the requirement to perform Specification 4.8.1.1.2.d.7.b within 5 minutes after completing the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run of the diesel generator. This is a one time exemption since compliance with this specification is intended for future tests.

Justification and Safety Analysis The requirement to perform a test loading of the diesel. generator with accident loads within 5 minutes after completion of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run is a new require-ment added to the Technical Specifications which were issued on June 12, 1981 with the 5% power license. The Technical Specification in effect before June 12, 1981 required the diesel generators to be loaded with blackout loads within 5 minutes after completion of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run. To comply with the new specification at this time would result in a 4 to 8 week delay in the plant startup since another integrated ESF test would be required.

The requested exemption is justified from both a technical and a safety stand-point for the following reasons:

1) The emergency start signal to the diesel generators is identical for blackout and accidents.

2)- The loading sequence is similar for both blackout and accident loads.

3) A successful " hot restart and load test with blackout loads of both diesel generators was performed during preoperational testing. This testing was performed with an accelerated sequence (2 seconds between

. load groups vs a commited 5 seconds between load groups).

4) A successful test loading of both diesel generators with accident loads was performed during preoperational testing.

5) The " ambient" conditions for the diesel generators include jacket cooling water temperature at 150 F (full load jacket cooling water temperature-is 165-175 F) and lube oil temperature at 150 F (full load fuel oil temperature is between 166 -173 F). Thus in a " normal" start the diesel generator must cope with elevated temperatures which approach those temperatures that exist 5 minutes after shutdown.

6) The response of the diesel generators to the sequencing of accident 1 'ds is similar to the response to blackout loads as shown in the following table.

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l ESF (ACCIDENT) LOADING Minimum Load Group Voltage (% Nominal) Frequency (Hz)

ESF (Accident) Loading Blackout Loading Min. Voltage Min. Voltage

(% Nominal) Freq. (Hz) (% Nominal) Freq. (Hz)

Sequence No.= A B A B A B A B 1 82.7 79.9 60.1 88.7 89.0 58.4 59.3 2 101.4 107.8 59.7 102.1 107.3 59.7 60.2 3 (5) 98.4 97.3 59 4 98.9 98.8 59.7 60.1 4 (6) 96.4 90.7 59.8 86.4 85.9 59.3 60.0 5 (7) 97.9 96.1 60.1 93.1 94.9 59.7 60.1

• Blackout sequencing logic bypasses Sequences Nos. 3 and 4 (RHR and Contain-ment Spray Pumps) since these loads are not required for blackout. Instead the sequencer goes to Sequence No. 5 and continues from there.

The above discussion demonstrates that the intent of the Technical Specifications has been met with the testing that has been performed. Duke Power Company con-cludes that repeating the integrated ESF test to verify the diesel loading capability after a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run is not necessary. There are no health and safety consequences arising from the requested waiver.

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'McGUIRE NUCLEAR STATION Technical Specification 3/4.3.3.7 Fire Detection Instrumentation ~

. Proposed Changs

' Revise Table 3.3-11, Fire Detection Instruments,-as shown on attached table to reflect the actual number of fire detection instruments installed in the Station. ,

q Justification-Fire Zone 106 - The minimum number of detectors required in this fire zone by .

National Fire Protection Association (NFPA)-Code 72F-1974 is two ionization

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(smoke)~ detectors _and two heat / rate of. rise detectors. The current number of detectors _ listed in the Technical Specifications is in error since it lists the number of detectors located in the corresponding Unit 2 fire zone which ,

is larger and requires additional detectors.

Fire Zones 147 through 150 - Each of these fire zones contain one heat / fixed

. temperature detector to-monitor the temperatures around the Reactor Coolant Pump (RCP) motors. This detector is-a-long cable type detector which wraps- ,

around the RCP motor several times. This installation complies with NFPA 72E-1974.

The number of smoke detectors in each fire zone is dependention the amount of

. cable located in each zone. Thus, for Fire Zone 148 only one smoke detector is required,;whereas three detectors are required in Fire Zone 149 and four detectors are required in Fire Zones 147 and 150. The number and location of these smoke detectors is in compliance with~NFPA 72E-1974.

All of_the above detection devices have been installed in accordance with the .

criteria in NFPA 72E-1974 and in the McGuire Fire Protection Hazards Analysis. [

There is no effect on public health and safety associated with the proposed  ;

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