ML19332E463

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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.2420'W. 26thfAve. Suite 100u, Denver, Colorado -80201 Canpany of Chd t:

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November 30,L1989 I"

~.

Fort St. Vrain'~

h"

' Unit No.' 1

,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

',;f

SUBJECT:

PSC Response to Generic Letter-

~

89-21 s

U.

REFERENCE:

Generic Letter 89-21, dated

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

'I

'W*

-Gentlemen:

In.. the ' reference -cited above, the NRC transmitted Generic Letter 89-21 ' requesting. the implementation status 'of unresolved safety 4

issuesi(USle). of Generic Letter 89-21-included.a lict of USIs for which final clesure has been reached. -Attached to-this-t

. 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 f s'

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' HLB /DCG:dcg ik Attachment M

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<Attschment.

$n to P-89451 t

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'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

^'

b Attcchr..hnt s

C to P-89451' f

Page'2 of *

-- a z

b A-17 Systems' Interactions - Undergoing internal review for p.

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

4 Vrain during defueling and decommissioning, c

p'

'A-24/MPA Oualification of Closs IE' Safety-Related Equipment -

B-60*

PSC actions are complete as strted in PSC Reference 4, o

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

]'

W,

'A-47*

Safety Implicction of control Systems;- Recently.

i J

tih

'+b

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

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• i A-48;

. Hydrogen. Control Measures and: Effects of. Hydrogen g

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

' design...

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,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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-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)-

' 6).

PSC Letter, Williams to Document Control Desk, dated July 15, 4

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

15) :NRC Letter, Gagliardo to Williams, dated July 21, 1987 (G-87245) s 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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