ML20210N883

Forwards Request for Addl Info on 861230 & 870115 Submittals Re Analysis of Firewater Cooldown from 82% of Full Power

ML20210N883
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/03/1987
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-63576, NUDOCS 8702130240
Download: ML20210N883 (4)

Text

-r ,

l

• ' February.3,'1987 _

n t

. Docket No. 50-267 ..

.\ ',

Mr. R. 0.--Williams, Jr.

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

4 )

Dear Mr. Wil11ws:

y-

SUBJECT:

ANALYSIS OF FIREWATER C00LDOWN FROM 82% POWER OPERATION -

REQUEST FOR ADDITIONAL INFORMATION j,

>p ~ i We are reviewing your submittals dated December 30, 1986 and January 15, 1987 (P-86683 and P-87002) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are .

requesting 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 0MB clearance is not required under P.L.96-511.

SincereQ, /

i

(

I Original signed by- 3 i

Kenneth L. Heitner, Project Manager Standardization and Special- 1.

Projects Directorate.

Division of PWR Licensing-B Office of Nuclear Reactor Regulation-

Enclosure:

As stated i.; cc w/ enclosure:

~

See next page  !

DISTRIBUTION:

LUncRet F13t"=

l NRC'PDR' i

Local PDR PBSS Reading PNoonan KHe'itner Clynch HBerkow CThomas h-

, a1 ORNL n tn c OL ch ow E Iz aI 01/3&87 01/ 3 /87 01/h/87 01/b /87 01/p}/87 01/g/87 l 8702130240 870203 l PDR ADOCK 05000267 p PDR

/ jo, UNITED STATES 8 ' ,o NUCLEAR REGULATORY COMMISSION h y$ WASHINGTON, D. C. 20555

% # February 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 -

REQUEST FOR ADDITIONAL INFORMATION We are reviewing your submittals dated December 30, 1986 and January 15, 1987 (P-86683 and P-87002) concerning your analysis of a firewater cooldown from 82% of full power. In order to complete this review, we are requesting 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, LSs LR Kenneth L. Heitner, Project Manager i Standardization and Special

Projects Directorate .

Division of PWR Licensing-B l Office of Nuclear Reactor Regulation l

Enclosure:

As stated cc w/ enclosure:

See next page

{

l l

l

4.

li < .

Mr. R. O. Williams ,

Public Service Company of Colorado Fort St. Vrain 1

cc:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company- Department of Health E

-of Colorado 4210 East lith Avenue-P. O. Box 840. Denver, Colorado 80220 Denver, Colorado 80201

Mr. David Alberstein, 14/159A Mr. J. W. Gahm, Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 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 i

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 Program Room 900' Coordinator 55015th Street Public Service Company of Colorado Denver . Colorado 80202 2420 W. 26th Ave. Suite 100-D Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative Radiation Programs Environmental Protection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413

,?

s.

s ,

4 Enclosure Request for Additional Information Concerning Firewater Cooldown Fort St. Vrain Docket No. 50-267

1. Attachment 4 to P-87002, page 13, describes certain repairs and manual actions that might be required in the event that one loop is '

incapacitated by a high energy line break and there is a coincident single failure of the power supply for the other loop. Describe the nature of the repairs and associated manual actions. Also, provide a target date for complete implementation of this process including procedures, training and physical plant modifications..

2. It is our understanding that your analysis assumes that the liner cooling system does not operate during the 90 minute' loss-of-forced-circulation cooling, assumed for a firewater cooldown. Provide an analysis that demonstrates that no damage will occur to the upper head liner during-this period as a result of heat transfer _from the reactor Core.

3. Provide a description of the general strategy that will be used by the operators to maintain the correct helium flow to achieve the desired subcooling margin at the steam generator outlet and yet not exceed the fuel failure temperature in the reactor core.

4. Provide your target date for completion of the confirmatory review of other FSAR analyses to verify the adequacy of the steam generator heat transfer sections.

5. Are orifice valves reset to equal-flow positions prior to starting the circulator for cooldown?

i 6. Provide a copy of Proto-Power Calculation No. 82-09.

I

7. Provide a basis for 125 gpm flow to booster pumps. This basis should provide a flow calculation for the water turbine train, losses through the water turbine and performance curves for the booster pumps.

I 8. Provide summary documentation of the theory, assumptions and results of the GA " alternative calculation" used as a verification check as required by 10 CFR 50, Appendix B. Summarize any supporting data from tests of the firewater or " simulated firewater" systems.

9. Justify the absence (or lack) of transient calculations for the

- firewater flows.

_. _ . . _ . . _ _ . . _ _ _ _ . _ _ _ __ _ _ .__ _ ___ _ . _ . _ _ _ . _ _ _ _ _ _ _ . - _ _ -.__ ___ -