ML20141P193

Forwards Info/Clarification for Open Items & Revised App R Fire Protection Evaluations (Repts 1-4) & Fire Hazards Analysis & Evaluation of Bldg 10 (Rept 5)

ML20141P193
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/14/1986
From:	Walker R PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
Shared Package
ML20141P194	List: ML20141P193
References
P-86209, TAC-54373, NUDOCS 8603190132
Download: ML20141P193 (8)

Text

..

PUBLIO SEltVICE COMPANY OF COLOllADO i

P.

O.

BOX 840 DENVER.

COLORADO 80201 i

R.F. W ALKER meseENT March 14, 1986 i

Fort St. Vrain Unit No. 1 i

P-86209 l

Director of Nuclear Reactor Regulation I

U.S. Nuclear Regulatory Comission i

Washington, D.C.

20555 l

Attn: Mr. H.N. 8erkow, Project Director i

Standardization and Special Projects Directorate Docket No. 50-267

SUBJECT:

Appendix R Evaluation

REFERENCE:

1) PSC letter Walker to Berkow dated 12/20/85 (P-85488)

Dear Mr. Berkow:

This letter provides additional information and/or clarification based upon the February 26, 1986 phone call between the NRC staff, Public Service Company (PSC), and TENERA Corporation. Attachment 1

)

to this letter provides that information/ clarification for those l

items which we understand the NRC staff considers open. Attachment 1 I

comits to the following future submittals:

Item Submittal Date l

Steam Generator Analysis September 1, 1986 Valve Postion Verification Approach April 4, 1986 Details on Manual Actions and Timing April 4, 1986 l

l 0603190132 960314 I

P,DR ADOCK OSOg7 poG l

Ill

P 86209 March 14, 1966 Please note that the April 4, 1986 submittals will also include page changes to incorporate the manual pressurtration system for the Helium Circulator Brake and Seal System which was installed as part of the Environmental Qualification Program to justify operation at 355 power level.

This is considered an enhancement to the fire protection shutdown models.

In addition, PSC is courtitting to a Fire Protection Program Plan by October 1, 1986. A develop description of this plan is included as Attachment 2 to this letter.

The intent of this schedule is to provide sufficient infomation those NRC through the April 4,1986 submittal in order to close out concerns requiring resolution before a $afety Evaluation Report can be issued.

Also enclosed with this letter are 20 copies of the page changes to the Fort St. Vrain Appendix k Fire Protection Evaluation (Reports 1 thru 4) and the Fire Hazards Analysis and Evaluation of Building 10 (Report No. 5) discussed in the February 26th phone call.

Please f

arrange to have tFese changes incorporated into these reports.

If you have any questions please contact Mr.

M.

H. Holmes at (303)480-6960.

Very truly yours.

A s1 kddbv he-lYinh%

R. F. Walker, resident RFW/N:pa Attachments The following provides addltional infomation/ clarification requested by the NRC staff. The numbers in the left hand margin respond to the l

in the December 20, 1986 letter to the NRC q(uestions/ responses reference 1).

14.

Delays encountered in re entering the Service Water i

1 Pump Building following suppression of a fire would still allow sufficient time for verification of valve positions and required valve repositioning in order to institute required service water flow to support l

restarting a circulator within 1 1/2 hours.

The l

1. hour delay for re. entry into this area will not impact the fimes noted in response to Question No. 13.

Additionally, because the service water strainer is back-flushed weekly, this will not be an action I

required for safe shutdown.

The back flush can be perfomed manually.

l 2a./2b.

Page changes referred to in the response to Question l

No. 2a are included with this letter.

P$C will review further the adequacy of present controls to assure the proper alignment, including t

valve positioning of systems within the Appendtn A i

l shutdown model. Consideration will be given to the need for enhanced controls or survelliance.

The i

results of this review will be described in our i

April 4, 1986 letter.

3a.

A further evaluation has confimed that a C$T l

inventory of appronimately $,000 gallons would be required in order to allow for reflooding of the ESS l

section of the steam generators in one loop, flooding of steam lines down to the turbine stop valves, and l

" float" required for cycling of level in the turbine AccordinglyItevedTechnical water drain tank.

$pecification limits are still not be to be required.

r to P-86209 4.

The results of the analysis described in PSC's Response in our December 20, 1985 letter demonstrate that cooldown under the low liner temperature conditions described without use of PCRV liner cooling will not result in degradation of the PCRV, and liner integrity will be maintained.

6a.

The revised Table 3.2 to Report No. I referred to in the PSC response is included in the page changes attached to this letter.

6b.

Using additional criteria to search for modifications to the ACM system, PSC has identified the following additions:

CN-1242 - Add the Technical Support Center to the l

ACM Switchgear i

CN-426 - Add the ACM as a source for Security Back-up CN-524 - Disconnect loads from the IACM, and add to either the ACM MCC or the ACM switchgear.

CN-2247 - Replace ACM Diesel Batteries 7b.

As noted in our previous response, the spool pieces M-3129 and M-21834 are not used in the Fire Protection shutdown model since alternate flow paths through existing piping are used. The spool pieces for the HTFAs have been replaced with "hard pipe" by CN-2142, i

9.

The Steam Generator analysis described in reference 1 l

will be submitted by September 1,

1986.

The time taken to establish the cooling flow path within the 1 l

1/2 hour time frame and pressure control location will be taken into account in this analysis.

11.

PSC will undertake a review of flow paths and one-line diagrams relied on in the Appendix R shutdown models.

l This review will identify the functional, qualification, or surveillance tests that have already i

j been performed to demonstrate the capability of portions of the flow paths / electrical distributions.

l Additionally, normal operating conditions will be i

considered where these demonstrate portions of the l

flow path or electrical distributions in the shutdown model.

The review will define appropriate tests for

8 FIRE PROTECTION PROGRAM PLAN PSC is undertaking development of a Fire Protection Program Plan in occor.

donce with the requirements of 10 CFR 50.48(a1. The Program Plan will consolidate and update Fire Protection Program commitments and details presently contained on the Fort St.Vrain docket. The Program Plan willinclude o description of the nature of the Fire Protection Program of Fort St.Vroin, positions responsible for implementing the program, administrative and periodic test provlsions concerning the Program, fire suppression and detection systems Installed in the plant, on updated Fire Harords Analysis for each plant fire oreo, and on updated comportson to Appendix A of BTP 9.51.

Additionally, the Program Plan will include o description of the Appendix R functional qualifico.

tion testing review. Considerotton will otso be given, to incorporation of appropriote commitments and details in the Program Plan IE ' order to offow removol of fire protection equipment from the Fort St.Vratn Technlcol Speelft.

cottons, similar to approaches being considered by the NRC staff on other plants.

4 Attachment I to P.86209 r

portions that have not been demonstrated, or have not been tested in the same manner as proposed in the i

J shutdown model 1.e.,

manual control in lieu of automatic control.

i Tests will be performed where not adverse to equipment protection or public health and safety.

The Fire Protection Program Plan will incorporate a sumary of the above review, the results, and subsequent tests i

that are performed.

12a./12b./13. PSC is undertaking an area by. area investigation to define the minimal manual operations that would have

[

i to be taken by operators, given a fire in each fire area. This review will be completed and details included in our April 4,

1966 submittal.

This l

information is espected to supplement that contained I

in our December 20, 1985 submittal, and further substantiate the adequacy of the shift crew to implement the shutdown model. This information will i

be factored into the appropriate operating procedures.

Any significant changes uncovered while preparing those procedures will be submitted to the NRC.

n PAGE REPLACEMENT INSTRUCTIONS REPORT NO. I REMOVE INSERT COMMENTS Title Page Title Page Changed to Rev. 5.

Section 2, Table 2.I-l Section 2, Table 2.l-1 Editorial changes, plus valve added Entire Table Entire Table to eliminate spurious concern, and L.P. Separator deleted from shut-down model.

Section 2, Table 2.1-2 Section 2, Table 2.1-2 L.P. Separator deleted from shut-Page 2 Page 2 down model.

Section 2, Toble 2.1-3 Section 2, Table 2.1-3 Editorial changes plus valve addi-Entire Table Entire Table tions to prevent flow diversions.

Section 2, Table 2.1 -4 Section 2, Table 2.1-4 Editorial changes plus volve addi-Entire Toble Entire Table tions to prevent flow diversions.

Section 2, Toble 2.1-S Section 2, Table 2.1-5 Deleted manual operations since not Page 2 Page 2 required (valves are control protected).

Section 2, Table 2.1-6 Section 2, Table 2.l-6 Editorial changes, plus valve O,

Entire Table Entire Table changes to reflect shutdown model refinements (refer to Note l/ at end

~

of table).

Section 2, Toble 2.1-8 Section 2, Table 2.1-8 Deletion reflecting correction to ACM support components.

Figure 2.1-9 Figure 2.l.9 Changes to flow rates, to reflect revised booster pump capability and steam generator conditions.

Figure 2.1-10 Figure 2.1-10 Revised to reflect shutdown model'-

changet deleted steam / water drain.

Figure 2.1-l l A Figure 2.1-lI A Revised since TD service water loads are isolated and suf ficient flow Is ovallable for all RB loads.

(See Note I of Table 2.14.)

Figure 2.1-l !B Figure 2.1-llB Revised since sufficient flow is ovallable for all RB and TB foods.

(See Note I of Table 2.14.)

O DC-84-21 1

Rev. 5

PACE REPLACEMENT INSTRUCTIONS I

REPORT NO. l (continued)

REMOVE INSERT COMMENTS Section 2, Table 2.2 1 Section 2, Table 2.2 1 Revisions and additions consistent Pages 3 through 8 Pages 3 through 8 with shutdown model.

Section 2, Teble 2.3-2 Section 2, Table 2.3 2 Editorial change.

Page 2 Page 2 Section 3, Table 3.1 Section 3, Table 3.1 Revisions consistent with shutdown Entire Table Entire Table

• model changes and previous table changes.

Section 3, Table 3.2 Section 3, Table 3.2 Revisions showing ACM components Entire Table Entire Table and equipment numbers; deletion of Breathing Air Compressors.

i O

Not all pages changed, but all were reploced for ease of insertion.

O DC-84-21 2

Rev.5

.