ML20202G683

Forwards Revised Page 5 to Attachment 1 of Util 860528 Response to NRC 860502 Request for Review of Approved Regulatory Requirements.Info on Multi-Plant Actions F-13 & F-14 Revised

ML20202G683
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/09/1986
From:	Brey H PUBLIC SERVICE CO. OF COLORADO
To:	Berkow H Office of Nuclear Reactor Regulation
References
TASK-1.A.1.1, TASK-1.A.2.1, TASK-1.C.1, TASK-1.C.5, TASK-1.C.6, TASK-1.D.1, TASK-1.D.2, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.D.1, TASK-TM P-86455, NUDOCS 8607160057
Download: ML20202G683 (3)

Text

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Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 July 9, 1986 Fort St. Vrain Unit No. 1 P-86455 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No.

50-267

SUBJECT:

Regulatory Information Tracking System

REFERENCE:

1) NRC Letter, Heitner to Walker, dated May 2, 1986 (G-86241) 2)

PSC letter, Brey to Berkow, dated May 28, 1986 (P-86399)

Dear Mr. Berkow:

In Reference 1,

NRC requested that PSC review a list of Fort St.

Vrain-specific approved regulatory requirements and provide the status of each item.

Reference 2 transmitted PSC's revised response to the NRC's request.

In Reference 2, the information provided for items MPA F-13 and MPA F-14 was incomplete. To correct this, please replace Page 5 of Attachment 1 to Reference 2 with the attachment enclosed with this letter.

8607160057 860709 PDR ADOCK 05000267 P

PDR h0 D

s

~

P-86455

/

Page 2 July 9, 1986 If you need further information on any item in this letter, or if you have any further questions, please contact Mr.

M.

H.

Holmes (303) 480-6960.

Very truly yours, H._L. Brey, Manager 1 Nuclear Licensing and Fuels HLB /KP0:kb Attachment t

i 3

l I

(o' P-86399 Revision 2 Page 5 MPA TAC STATUS SUBJECT DATE CL REF F-02 M44091 C

I.A.1.1 SHIFT MANNING MAR.

0586A)C) G-83369 1983 0651A)B)

F-03 M44163 C

I.A.2.1 UPGRADE SR0 & R0 MAR.

0587 P-81002 TRAINING 1982 G-82084 F-04 M44234 P

I.C.1.2/3.A E0PS - INADEQUATE 4th RE-1126J)

P-86331 CORE COOLING GUIDELINE FUELING (EST.

JUNE, 1988)

F-05 M44304 P

I.C.1.2/3.8 PROCEDURES 4th RE-11218)

P-85386 GENERATION PACKAGE (PGP)

FUELING G-85345 (EST.

JUNE, 1988)

F-06 M47217 C

I.C.5 FEEDBACK OF OPERATING MAR.

0564A)

G-82084 EXPERIENCE 1982 0589 INTERNAL MEM0 F-07 M47289 C

I.C.6 CORRECT PERFORMANCE SEPT.

0619 P-82424 0F OPERATING ACTIVITIES 1982 G-82370 F-08 M51162 C

I.D.1.1 DETAILED CONTROL ROOM AUG.

1218 P-85454 DESIGN REVIEW (DCRDR) 1985 F-09 M51242 P

I.D.2.

SAFETY PARAMETERS 4th RE-0975 G-85345 DISPLAY SYSTEM (SPDS)

FUELING VARI.

(EST.

JUNE, 1988)

F-10 M44375 C

II.B.1.

REACTOR COOLANT SYSTEM MAR.

0593 P-80438 (RCS) HIGH POINT VENTS 1982 G-82084 F-11 M47940 C

II.B.2 PLANT SHIELDING MAR.

0594 P-80438 1983 0595 G-83117 F-12 M44443 C

II.B.3 POST ACCIDENT JAN.

1202 G-86028 SAMPLING 1986 AND P-85446 i

OTHERS F-13 M44513 C

II.B.4 TRAINING FOR 1981 598A)C)

INTERNAL MITIGATING CORE DAMAGE MEM0 F-14 M45345 C

II.D.I.

RELIEF VALVES MAR.

N/A G-82084 AND SAFETY VALVES TRAINING 1984 TO FSV

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