ML17317B341

Summary of 790514 Meeting W/Util in Bethesda,Md Re Status of Containment Purge Review & Related Subj

ML17317B341
Person / Time
Site:	Cook
Issue date:	06/12/1979
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17317B342	List: ML17317B341
References
NUDOCS 7907240493
Download: ML17317B341 (15)

Text

JUhf 1 2 )gyp h~~ggPg Jocket Nos.

6 W a

-316 LICENSEE:

INDIANA'AND MICHIGAN POHER. COMPANY FACILITY:

D. C.

COO): UNIT NOS. I AND 2 2

SUBJECT:

HEETIHG SUYNRY - CONTAINNENT PURGE The Licensee met with the staff on Hay 3'I, 1979 in Bethesda to discuss

'he status of review of. the containment purge and related subjects.

The Ifst-of attendees is.attached as Enclosure 1.

The importance of the staffs desfres to limit the purging of operating reactors was stressed with the 'licensee.

The licensee had previously requested unlimited purging based on the successful tests of the '24" valve fn the upper containment.

The licensee currently has a tech spec restriction on purging Un]t 2 during modes I thru 4 and has imposed an administrative contro'I on Unft I purgfng during modes I thru 4 to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year.

The operators do not have authority to purge on Unit I; request a}e forwarded thru the shift operations engineer to t)ie operations group for approval.

Purging's used for maintenance and surveillance

~

operations to forgo the use of scott air pacts and reduce dose accumu-Iatfops due to the slower operations in the air pacts.

Purging can provide for air cooling,- afr purification, and humidity control if needed for ~ufck entry to the containment.

Otherwise, systems are avafTable forcomfort control" although they take longer.

For fmment=.radfologfcaI'eleasses, the internal systems are used; not purging.

The testfng of the 24" isolation valve in the upper containment was performed with a screen also designed to limit pressure on the valves.

Unit 2 has had screens installed since construction.

Unit I installed similar screens during the current refueling outage.

The 'largest valve is 30".

The test results have been submitted to the NRC and applies to both Units due to simi'lar configuration and valve manufacturer.

Unit 2 has not purged during nodes I thru 4.

Unit I has purged about 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> in the past year in modes I thru 4.

As such, this represents, sonauhat a typlca1 upper and 'loner 1lnl't to purging during operations.

qydyZ ggg9 ~,

OFFICC9N'UltNAlaEW DATE~

'HRC PORM 518 (9.76) eNRCM ONO s

~

~

. II.S. OOVRRNMCNT FRINTINO OIPFICRI Ia'I~

aaa yaa

N

Yeetfng Summary for D. C.

Cook Units 1 5 2 The licensee, provfded data on the valves, actuators, and purge system schematic (Enclosure 2).

To complete the information request on the containment purge, the licensee will also provide:

1.

Cost estimate for screen installation, 2.

Typical temperature and humidity fn containment,'.

Details of the Unit 1 purging (120 to

'26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />),

and I

4.

Information on restricted (Unit 2) versus unrestricted (Unit 1) purge fn terms of cost and radfatfon exposure.

Detailed discussions were also held on the intent of the hRCs November 28,

'l978 leter on containment purge during normal plant operation; specfffcally on manual override of. safety actuation signal circuits.

The licensees'nnderstanding had been documented in their January 4, 1979'letter to the NRC.

After careful consideration to the t/RC's con-

cerns, the licensee agreed that both interim and.final fixes were re-quired.

The interim fixes would be incorporated in both units before return to power and a schedule developed for the final fix>>hen the fix is proposed by AEP and reviewed by the NRC.

The interim ffx will be proosed by AEP within a week following the meeting.

1

- Dave Nggfnton, Project ttanager Operating Reactors Branch gl Division of Operating Reactors

Enclosures:

List of Attendees Data for Actuators cc:* w/enclosures See next page OrnCC>

CURHAMCW DATC~

"fmR'ORB'1"

.DMi.g.g.into'

• O,t. OOVCRNMCNT RRINTINO Ol RICCI Ittt ttt 7 ~t

~ 0 ~

I 4(

gp8 AEQUI Wp0 Cy p %~

C O

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos.

50-315 and 50-316 JUN 1 2 197Q LICENSEE:

INDIANA AND MICHIGAN POWER COMPANY FACILITY:

D.

C.

COOK UNIT NOS.

1 AND 2

SUBJECT:

MEETING

SUMMARY

- CONTAINMENT PURGE The Licensee met with the staff on May 31, 1979 in Bethesda to discuss the status of review of the containment purge and related subjects.

The list of attendees is attached as Enclosure l.

The importance of the staffs desires to limit the purging of operating reactors was stressed with the licensee.

The licensee had previously requested unlimited purging based on the successful tests of the 24" valve in the upper containment.

The licensee currently has a tech spec restriction on purging Unit 2 during modes 1 thru 4 and has imposed an administrative control on Unit 1 purging during modes 1 thru 4 to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year.

The operators do not have authority to purge on Unit 1; requests are forwarded thru the shift operations engineer to the operations group for approval.

Purging is used for maintenance and surveillance operations to forgo the use of scott air pacts and reduce dose accumu-lations due to the slower operations in the air pacts.

Purging can provide for air cooling, air purification, and humidity control if needed for quick entry to the containment.

Otherwise, systems are available for "comfort control" although they take longer.

For imminent radiological

releases, the internal systems are used; not purging.

The testing of the 24" isolation valve in the upper containment was performed with a screen also designed to limit pressure on the valves.

Unit 2 has had screens installed since construction.

Unit 1 installed similar screens during the current refueling outage.

The largest valve is 30".

The test results have been submitted to the NRC and applies to both Units due to similar configuration and valve manufacturer.

Unit 2 has not purged during modes 1 thru 4.

Unit 1

has purged about 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> in the past year in modes 1 thru 4.

As such, this represents, somewhat a typical upper and lower limit to purging during operations.

Meeting Summary for D.

C.

Cook Units 1

8 2 The licensee provided data on the valves, actuators, and purge system schematic (Enclosure 2).

To complete the information request on the containment purge, the licensee will also provide:

1.

Cost estimate for screen installation, 2.

Typical temperature and humidity in containment, 3.

Details of the Unit 1 purging (120 to 126 hours0.00146 days <br />0.035 hours <br />2.083333e-4 weeks <br />4.7943e-5 months <br />),

and 4.

Information on restricted (Unit 2) versus unrestricted (Unit 1) purge in terms of cost and radiation exposure.

Detailed discussions were also held on the intent of the NRCs November 28, 1978 leter on containment purge during normal plant operation; specifically on manual override of safety actuation signal ci rcuits.

Th'e licensees'nderstanding had been documented in their January 4, 1979 letter to the NRC.

After careful consideration to the NRC's con-ce'ms, the licensee agreed that both interim and final fixes were re-quiredd.

The interim fixes would be incorporated in both units before return to power and a schedule developed for the final fix when the fix is proposed by AEP and reviewed by the NRC.

The interim fix will be proposed by AEP within a week following the meeting.

Enclosures:

List of Attendees Data for Actuators Dave Wigginton, roject Manager Operating Reactors Branch 81 Division of Operating Reactors cc:

w/enclosures See next page

Meeting Summary for D. C.

Cook Units 1

& 2 Docket Files NRC PDR Local POR ORBl Reading NRR Reading H. Oenton E.

Case V. Stello D. Eisenhut B. Grimes R. Vollmer A. Schwencer D. Ziemann P.

Check G. Lainas D. Davis B. Grimes T. Ippolito R. Reid V. Noonan G. Knighton D. Brinkman Project Manager GELD OI&E (3)

C. Parrish ACRS (16)

NRC Participants J.

Buchanan TERA Licensee Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, O.

C.

20036 David Oinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Mr. D. Shaller, Plant Manager Donald C.

Cook Nuclear Plant P. 0.

Box 458 Bridgman, Michigan 49106 Kenneth R. Baker 2874 Robin Hood Drive Stevensville, Michigan 49127

ENCLOSURE 1

LIST OF ATTENDEES AEP/COOK 1/2 MEETING Ed A. Reeves Ted Quay J.

T. Beard L. R. Nichols J. J.

Zudans E.

M. McKenna J. Kerrigan E.

G. Adensam Alan Wang R. 0. Smith T. J. Restivo R. f. Hall R.

P.

Rumble D. L. Wigginton Jude G.

Del Percio Robert C Carruth J. I. Castresana D. V. Pickett R. Kiessel NRC/DOR/ORBgl NRC/DOR/PSB NRC/DOR/EEB DOR/NRR DOR/EB DOR/RSB DOR/PSB DOR/PSB DOR/PSB BNL/GAC BN1/GAC BNL LLL

ORB1, NRR AEPSC AEPSC AEPSC CSB/DSS MEB/DSS

ENCLOSURE 2

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~ Atlitt)ItA. II)JNI)l+ IX).el)7 HANDLED SN MAY 30 1979 E. I. "HDHZE" CONNER C c" k ~'~l E'

P~iu+s April 12, 1979 Mr. Carl Yoder Baltimore Gas 6 Electric Co.

P.O.

Box 1475 Baltimore, MD 21203

SUBJECT:

Pratt Job No's.

7-4054-1 6 7-4054-2, 48" Butterfly Valves

Dear Mr. Yoder:

En rega'rd to your request for information concerning operator and valve torques for the subject 48" purge valves, I

am enclosing a computer printout of our valve torque.

')j']oe:- '

This printout shows the dynamic and bearing torque at.

various angles plus the seating and bearing torque which occurs at the closed position (angle

~

0 degrees) and the maximum value of dynamic and bearing torques and the angle at which they, occur.

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- I 't' I

As you can see, the maximum valve torque is 35,795 inch

=pounds at the closed position.

r, The operator; Bettis model T-520-CSR 4, has a rating of from 53,000 in-lbs. with the valve in the open position to 40,000 in-lbs. with the valve in the closed position, when being actuated by the spring, assuming zero air pressure.

When being opened with 80psig supply the operator rat-ing is from 100,000 in-lbs. with the valve in the closed'osition to 70,000 in-Ibs

~ with the valve open

~

~ 4 Keith'ehn KL/kad Enclosure cc:

J.

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11 / 79 VAl'E S IKEt VALVE TYPEt SHAF T DIA~ !

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OF FRCTN ~ t INLET PRESSURE t OUTLFT PHESSUREt F4'LOW RATE:

RENSITY t FULL OPEN DELTA P t SY ST Eb'OND IT I ONS t PIPE IN - PIPE OUT 48 INCHES ANVIL CLASS 65

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'9969 499,99 TD 4187 29381 18383 16858 9495 7624 4631 2367 8

TB 1285 924 383 95 29 18 3

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TO+TB 5313 21386 18686 16945 9524 7634 4635 2369

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