ML20197F367

Forwards Request for Addl Info on 860314 Submittal Re Steam Line Rupture Detection & Isolation Sys,For Response within 30 Days of Ltr Date

ML20197F367
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/07/1986
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Walker R PUBLIC SERVICE CO. OF COLORADO
References
TAC-60421, NUDOCS 8605150541
Download: ML20197F367 (5)

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May 7, 1986 Docket No. 50-267 Mr. R. F. Walker, President Public Service Company of Colorado Post Office Box 840 Denver, Colorado 80201-0840

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - STEAM LINE RUPTURE DETECTION AND ISOLATION SYSTEM (SLRDIS)

We are continuing our review of your submittal dated March 14,1986 concerning SLRDIS, together with related documents you have submitted concerning your equipment qualification program. We would appreciate your response to the enclosed request for additional information to amplify and clarify parts of your submittal.

We request that you provide this information within 30 days of the date of this letter.

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

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Mr. R. F. Walker, President Public Service Company of Colorado .

Post Office Box 840 Denver, Colorado 80201-0840

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - STEAM LINE RUPTURE DETECTION AND ISOLATION SYSTEM (SLRDIS)

We are continuing our review of your submittal dated March 14, 1986 concerning SLRDIS, together with related documents you have submitted concerning your equipment qualification program. We would appreciate your response to the enclosed request for additional information to amplify and clarify parts of

. your submittal.

We request that you provide this information within 30 days of the date of this letter.

The information requested in this letter affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L. 96-S11.

Sincerely,

%#1%k Kenneth L. Heitner, Project Manager Standardization and Special Projects Directorate Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure:

See next page l

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FORT ST. VRAIN '

REQUEST FOR ADDITIONAL INFORMATION EQUIPMENT QUALIFICATION (SLRDIS)

1. Since a high energy line break will result in a defined jet of hot water or steam in a limited area, justify your assumption that the entire length of thermistor cable in the steam line rupture detection and isolation system (SLRDIS) will be at the same temperature after a high energy line break. Further, because the entire length of a 200 ft. long thermistor cable must "see" a 55 F/ minute temperature change following a high energy line break in order to initiate a secondary system isolation signal, show that the SLRDIS response time to this condition is rapid enough to result in the required isolation prior to exceeding equipment qualification envelopes for essential plant shutdown equipment.

2. Discuss your plans to verify continued satisfactory operation of the SLRDIS after initial installation including your proposal to conduct periodic systematic tests of the SLRDIS in place. This discussion should include

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the technical specification modifications you plan to provide to accomplish periodic, in situ testing. Discuss hor you intend to verify the SLRDIS response time assumed in the safety analyses.

3. Discuss actions to be taken by plant operators in the event the pre-trip alarm temperature (135*F) is reached following a high energy line break (HELB) without causing the 55'F/ min. temperature change that would result in automatic SLRDIS actuation. Show that equipment needed for plant shutdown in such an event is not damaged by the HELB.

4. Provide the following information for our review (as noted in Attachment 1 to your letter P-86208, dated March 14,1986):

a. Resistance vs Temperature curve of the 9090-13 thermistor cable (200' lengths used at Fort St. Vrain) Dwg. No. 280023 Rev. A;

b. Sensor Center Conductor to Case Resistance vs Temperature - Initial and Final Curves after Accelerated Aging and Radiation Tests;

c. Functional Test of Alison Control After Seismic Test - dated 11/1985;

d. Equipment Qualification Package;

e. Seismic Test of Control Rack and Sensor Assemblies performed by Wyle Labs, 11/9/85;

f. Response Time Test of Thermistor Cable performed by Factor Mutual Research Corporation, 12/10/85; and

g. Qualification Test Report of 9090-13 Sensor Assembly (Doc. No.

ETR101), dated 2/7/84 for Application at Davis-Besse.

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5. Provide a discussion which indicates how the unavailability gokl of -

0.01 has been attained for the portions of the SLRDIS shown in: Figure 3 of Attachment 2 to your letter P-86208. If this discussion is.not for the complete SLRDIS, indicate what the unavailability is for the entire SLRDIS.

6. Confirm that in the event of a fire in those areas which may impact on the SLRDIS, safe shutdown of the plant is not affected.

7. Attachment 2 (Page 4.4-6c, action statement 1) to your submittal dated 12/31/85 (P-85456) discussing the SLRDIS system states:

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Power operation above 8% rated thermal power may continue provided the inoperable channel is placed in the bypassed or tripped condition--- ".

Provide justification for placing an inoperable channel in the bypassed condition.

8. Will a high energy line break in some areas cause increased temperatures in both the reactor building and turbine building? If so, show that you have accounted for this in the qualification of essential equipment.

9. Is there a potential for a steam line break at power levels 5E59% to be more severe than those at higher power levels because of the use of auxiliary boilers? If so, show that your analyses confirming equipment qualification has accounted for this potential.

10. Show that essential equipment required for shutdown, including instrumen-tation, exposed to spray from moderate energy line breaks is qualified to withstandsuchsprayandmaintain{tsTfunction.

t Mr. R. F. Walker 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 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. L. W. Singleton, Manager Public Service Company of Colorado Quality Assurance Division P. O. Box 840 Fort St. Vrain Nuclear Station Denver, Colorado 80201 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector

U.S. Nuclear Regulatory Commission P. 0. Box 640 Platteville, Colorado 80651 Kelley, Stansfield & 0'Donnell Public Service Company Building Room 900 550 15th Street Denver, Colorado 80202 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 1800 Lincoln Street Denver, Colorado 80203 l

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