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Responds to Generic Ltr 89-21 Re Implementation Status of USIs Requirements.Internal Review for Applicability of USI A-17 Re Sys Interactions Underway.No Util Actions Planned on USI A-40 Re Seismic Design Criteria Since Unit Shutdown
	ML19332E463
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/30/1989
From:	Brey H; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TASK-***, TASK-OR GL-89-21, P-89451, NUDOCS 8912070257
	Download: ML19332E463 (7)
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I" November 30,L1989 .

~. Fort St. Vrain'~

' Unit No.' 1 h" ,P-89451 i Q .

, II. S. Nuclear-Regulatory Commission t

, ' ATTN: Document Control Desk Li Washington, D. C. 20555 V ;/y .

Docket No. 50-267

N .

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SUBJECT:

PSC Response to Generic Letter-89-21 s

U.

REFERENCE:

Generic Letter 89-21, dated ,

'I October 19,-1989 (G-89376)

'W* -Gentlemen: 'I In.. the ' reference -cited above, the NRC transmitted Generic Letter 89-21 ' requesting. the implementation status 'of unresolved safety 4 issuesi(USle). Enclosure 1 of Generic Letter 89-21-included.a lict <

t of USIs for which final clesure has been reached. -Attached to-this-

. letter is a summarv of the implementation status of USIs relative to Fort St.-Vrain.

In ' a telephone . conversation on . NovemL e 2, 1989, Public Service

, f-Company of ' Colorado (PSC) discussed the status of these items with E Mr. Peter Erickson and Mr. - Kenneth Heitner of the NRC staff. This' "

/ letter . documents our l mutual onderstanding of the USIs and their

' applicability to Fort St. Vrain.

Should you have any questions concerning this matter, please contact Mr.; David Goss (303) 480-6959 for further assistance.

t Sincerely, ;

,4 *T1AA n-<x M 4.-

H. L. Brey, Manager, Nuclear Licensing and Resource Management

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<Attschment.

E.. $n to P-89451 t f 'U' :Page 1 of 5-h c ' Th'is attachment , lists the ' implementation ctatus of USIs . as they

- y relate 1 to. . the . Fort St.;Vrain Nuclear Generating Station. Issues 1 determined to be applicable by . the NRC staff in the referenced telephone call- are identified by an asterisk (*) in this attachment.-

, " References cited are Elisted .at 'the end. of this attachment. Ite as > >

p underlined indicate PSC and/or NRC documentation available to' support ,

^L -conclusions; reached.

[j; J . . _ _ . . ._____.____..____...... ___....._________....__..._____.. ..

A-1* Water hammer - Evaluated as applicable to Fort-St.

Vrain-and found. acceptable by the staff in NRC Reference 20. Additional PSC information documented in PSC References 6 and 7.

A-2/MPA D-10 ' Asymmetric Blowdown 'soads on Reactor Primary Coolant Systems .Not app'.Acabla to the HTGR design. .

A-3 Westinghouse Steam Generator Tube Integrity - No ,

further PSC actions planned. PSC response documented-in PSC Reference 1. "

A-4 CE Steam Generator Tube integrity - See USI A-3. ;

A B&W Steam Generator Tube Integrity - See USI A-3.

]'

-A Mark I Cantainment Short-term Program - Not cpplicable to the HTGP design.

A-7/D-01 Mt.rk I Long Term Program - Not applicable to the HTOR design.

A-8 M6rk II Containment Pool Dynemic Loads - Not applicable to the HTGR desjgn.

A-9* . Anticipated Transients Without Scram - PSC actions are complete as stated in PSC Reference 5 and as accepted by the staff in NRC References 16, 18 and 19.

A-10/MPA B-25 BWR Feedwater Nozzle Cracking - hot applicable to Fort St. Vrain.

A-11 Reactor Vessel Material Toughness Not applicable to l .the HTGR design, but evaluated in response to Generic Letter 88-11 NRC Reference 21 as documented in PSC Reference 8.

A-12 Fracture Toughness of Steam Generator and Reactor Coolant Pump Sapports - Not applicable to the HTGR

. design.

1 rp

^' '

s ... Attcchr..hnt b C to P-89451' f Page'2 of *

-- a z

b , A-17 Systems' Interactions - Undergoing internal review for

p. 4 applicability, if any, to systems required at Fort St.

c Vrain during defueling and decommissioning, p' 'A-24/MPA Oualification of Closs IE' Safety-Related Equipment -

o B-60* PSC actions are complete as strted in PSC Reference 4, !

li and as accepted by the staff NRC References 13, 14 and 15. 7 A-26/MPA'B-04 Reactor Vessel Pressure 'reansient Protection - Not applicable to the HTGR design.

A-31 Residual Heat Removal Shutdcen Requiremente - Not-applicable to Fort St. Vrain in a defueling or decommissioning status.

A-3f NPA C-10 Centrol of Heavy Loads hear Spent Fuel - PSC actions and C-15* are complete as stated in PSC Reference 2 and have '

been accepted by the staff in NRC References 10 and 11.

A-39 . Determination of SRV Pool Dynamic Loads and

-Pressure Transients - Not applicable to the HTGR

' design.

A-4C Seismic Design Criteria - No PSC actions planned as Port-St. Vrain is permanently shutdown.

A-42 Pipe Cracks in Boiling Water Reactors - Not applicable to the HTGR design.

A-43 Containment Emergency Sump Performance - PSC responded to this issue in PSC Reference 3 and the staff concurred with PSC's position'in NRC Reference-12. ,

A-44* Station Blackout - No further PSC actions are required as stated in PSC Reference 5 and as accepted by the staff in NFC Reference 18.

A-45 Shutdown Decal Heat Removal Requirements - Not applicable to Fort St. Vrain as part'of an Individual Plant Examination (IPE) for Severe Accident Vulnerability, per PSC References 5 and 9, and as ,

accepted by the staff in NRC Reference 18.

A-46* - Seiemic Qualification of Equiprent in Operating Plants No narther PSC actions are requ ued as stated in PSC Reference 5 and as accepted by the staff in NRC Reference 18.

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"(, Page 3'of 5: :)

(y :% ;q l 0 ei.e W, . , 'A-47* Safety Implicction of control Systems;- Recently. ]'

m+

J determined by PSC to be not applicable to' Fort St.- a i

tih '+b

, .Vrain-(PSC memo NLG-89-0767).. ~ !

sy ,

...~ i y-[ * ,

i A-48; . Hydrogen. Control Measures and: Effects of. Hydrogen '

g ' '

Bu ns on Safety. Equipment'-1Not applicable to the-HTGR -;

"J ' design . .. i f, r, , _ , ,-

,s 1 8

.h A-49/

~

Pressurized Thermal Shock - PSC responded,to'this I V '

'issueil:.. PSC Reference _4 and the staff: accepted'PSC's position in NRC Reference'17.

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to P-89451

, Page 4 of 5' -1 3

REFERENCES APPLICABLE TO US1s AFFECTING FORT ST. VRAIN-

-i s.

PSC References .y

^

?

1);. 'PSC Letter, Brey to Johnson, dated July 11, 1985-(P-85244)

2) .PSC Letter, Warembourg to Butcher, dated October 15, 1985 ,

, :(P-85361).

3) -PSC' Letter,:Brey to Berkow, dated' June 17, 1986 (P-86381)' =i

14) PSC Letter, Williams to Document Control Desk, dated December 7, 1988 (P-88419) i 5)' PSC Letter, Brey.to Document Control' Desk, dated January 20,

l 1989 (P-89026)- ,

4 ' 6). PSC Letter, Williams to Document Control Desk, dated July 15,

k 1988-(P-88250)-

7) -PSC Letter, Gahm to-Berkow, dated January 28, 1986 (P-86006)

8) PSC. Letter, Williams'to Docrment Control Desk, dated December 7, L1988 (P-88419)'-

9) PSC IIotter, Crawford to Document Control Desk, dated October ' 31,-

1989 (P-89422)

NRC References

.10) NRC Letter, Johnson to Lee, dated March 6, 1984-(G-84075)

11) NRC Gener.ic Letter 85-11, dated June 28, 1985 (G-8E254)

' " 12) NRC. Letter, Heitner to Williams, dated July 13, 1986 (G-86398) ,

?

13) NRC Letter,,Heitner to Williams, dated September 10, 1986 (G-86494) 14)~~NRC Letter, Merschoff to Williams,' dated April 3, 1987 (G-87108) ;

i s 15) :NRC Letter, Gagliardo to Williams, dated July 21, 1987 (G-87245) b 16). NRC-Letter, Callan to Williams, dated September 2, 1988 l (G-88363)

17) 'NRC Letter, Heitner to Willicms, dated January 12, 1989 L~ (G-89012) 18)L.NRC Letter, Heitner to Williams, dated April 18, 1989 (G-89137) l i

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