ML20207Q794

Forwards Second Request for Addl Info Re Util Analysis of Firewater Cooldown from 82% of Full Power Operation,Based on Review of 861230,870115 & 0217 Submittals

ML20207Q794
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/03/1987
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-63576, NUDOCS 8703090465
Download: ML20207Q794 (4)

Text

_ _ _ - _ _ _ _ _

March 3, 1987 Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840

SUBJECT:

ANALYSIS OF FIREWATER C00LDOWN FROM 82% POWER OPERATION -

SECOND REQUEST FOR ADDITIONAL INFORMATION We are reviewing your submittals dated December 30, 1986, January 15,and February 17,1987 (P-86683, P-87002 and P-87055) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are making a second request that you provide certain additional information. Our request for this information is enclosed.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, Original signed by Kenneth L. Heitner, Project Manager

, Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See.next page DISTRIBUTION:

tDectet file -

NRC PDR Local PDR PBSS Reading PNoonan KHeitner Olynch HBerkow Elantz RJenes CIhomas PBSS M PS ' P.8%^) , - PBRS onan XHeitner:ac Olydch HBerkow a tz RJ nes CThomas 0 % /87 02/ 2./87 0 % /87 02/y/87 Ogy87 OJ/63/87 0J/3 /87 8703090465 870303 PDR ADOCK 05000267 P PDR

A, '

6 Q IfQy Q !g<. (o, UNITED STATES

(* n NUCLEAR REGULATORY COMMISSION f ,E WASHINGTON, D. C. 20555

• " March 3, 1987 Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840

SUBJECT:

ANALYSIS OF FIREWATER C00LDOWN FROM 82% POWER OPERATION -

SECOND REQUEST FOR ADDITIONAL INFORMATION We are reviewing your submittals -dated December 30, 1986, January 15,and February 17, 1987 (P-86683, P-87002 and P-87055) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are making a second request that you provide certain additional information. Our request for this information is enclosed.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, w~ h.'

Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page

p t

( Mr. R. O. Williams Public Service Company of Colorado Fort St. Vrain cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Cenver, Colorado 80220 Denver, Colorado 80701 Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Bcx 25608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker P. 0. Box 840 Public Service Company of Colorado Platteville, Colorado 80651 Post Office Box 840 Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Commitment Control Progran Room 900 Coordinator 550 15th Street Public Service Company of Colorade Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite '1000 Arlingtcn, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Padiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413

- 3

% I

-w .,;

'i

Enclosure-Recuest 'for Additional Irformation Concerning Safe Shutdown Cooling Fort St. Vrain Docket flo. 50-267

1. What is the status of the hot and cold reheat header isolation valves during a firewater cooldown?

2. Are the valves either closed or operable for automatic closure should a leak develop'in the reheater tubes?

3. Are there initiating events for which this system is not qualified, or does not meet regulatory requirements, such as an earthquake or single fire?

A. What safety benefits would come from closing the valves before restoring helium circulation?

5. What safety benefits would come from being able to pressurize the reheater with dry gas before restoring helium circulation?

6. Page 14 of Attachment I to P-87055 refers to the results of special testing of si:nulated firewater supply to the steam generators and circulator Pelton drives. The text of Unusual Event Report 76/05A indicates that Test T-30 yielded only 540 gpm supply to the steam generator. What was the circulator speed achieved during this test?

What were the steam generator supply flow and circulator speed during Test T-30A7 Test RT-403 achieved circulator speeds in excess of 700 RPM on each circulator. What was the steam generator supply flow during RT-403? What circulator speeds and concurrent steam generator flow rates were obtained during any testing after installation of the emergency water booster pumps? What were the simulated firewater supply pressure (booster pump suction), steam generator back pressure, and Pelton wheel supply pressure during each of these tests for which data are provided?

7. SR 5.2.7.? is indicated to be performed with 115 psig suction pressure at the emergency booster pump from throttled condensate. Provide the results of SR 5.2.7.? in terms of booster pump suction pressure, booster pump differential pressure, circulator speed, simulated firewater flow rates from the booster pump and to the Pelton wheel, and primary system flow at rated helium inventory. Has SR 5.2.7.?

been performed in conjunction with simulated firewater flow to the steam generator? If so, provide the above results plus the steam generator flow and back pressure measurerents.