ML20237E714

Responds to 871019 Request for Addl Info on Changes to Tech Specs 4.3.10 & 5.3.8 to Delete Explicit Snubber Listing,Per Generic Ltr 84-13.Util Defined Snubber Spec Limiting Condition for Operation 3.7.10/SR 4.7.10 to Include Class I

ML20237E714
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/17/1987
From:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	Calvo J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
GL-84-13, P-87412, TAC-64439, NUDOCS 8712290143
Download: ML20237E714 (3)

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December 17, 1987 R.O. WILLIAMS, JR.'

Fort St. Vrain I T1ME PRESIDENT -

t NUCLEAR OPERATIONS Unit No. I s.

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t, V. S. Nucleuf Regulatory Commission

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ATTN: Docug nt Control Desk >

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' Attni! Mr. Jose A. .Calvo, Director '

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,; ' U$cket No. 50-267

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SUBJECT:

.Re span te.sto Request for-

' Additional Information y.'i ,

on' Changes to the Fort o . s ' ' ' St! Vrain Tech Specs f- -, ,

.' A,x.3.10 and 5.3.8 7 REFERENCES 1) PSC'Oatter Williams 1

(' to Berkcv, . dated l,, y, 12/13/B0(P-86671)

, 9- 2'/ Gener'ic Letter 84-13,'

dated 5/3/84

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. 1) NRC Letter-Heitner to Williams,-dated 10/19/87 (G-87375) y

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, 4) PSC Letter Lee tv

p Berkow, dated t U 11/27/85 (P-85448)-

Dear Mr. Calvo:

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3 This letter proVides 4eradditional information requested by te NRC j in Reference 3. In Reference 1, Public Service Company of Colorado .

(PSC) .; submitted an applicaricn to delete ~ the snubber tables and l ch-ify the snubber Techatcal . Specification pr Generic Letter 84-13 i /:,e ,

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P-87412 December 17, 1987 NRC Question:

The modification proposed by PSC indicates essentially that only

snubbers on Class I piping shall be operable. Clarification and confirmation is therefore 'needed if the specification for Fort St.

! Vrain Class I piping snubbers corresponds and' satisfies the requirement- for limiting condition for operation as specified in Generic Letter 84-13.

Requirement from Generic Letter 84-13:

"All snubbers shall be operable. The only snubbers excluded from this requirement are those installed on non-safety-related systems and then only if their failure of the system on which they are installed, would have no adverse effect on any safety-related system."

PSC Response:

The change that PSC proposed in the Reference 1 submittal was to delete the explicit snubber listing, consistent with Generic Letter 84-13. PSC did not revise the current requirement of LCO 4.3.10.a

.that "The reactor shall not be operated at power unless all shock suppressors (snubbers) on Class I piping systems... are operable..."

Therefore, snubbers which were previously covered by this Technical Specification will continue to fall under this specification. The current tabulation includes both those snubbers directly supporting Class I systems (Class I snubbers) and snubbers supporting non-Class

.I systems whose failure could adversely affect Class I systems (Class la snubbers), although this distinction is not defined.

In the Technical Specification Upgrade Program (Reference 4), PSC has defined the snubber specification, LCO 3.7.10/SR 4.7.10, to explicitly include both Class I and Class la snubbers. These definitions are included in the corresponding Basis.

PSC will continue to maintain the ope ability of all snubbers required to protect Class I systems.

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-1 P-87412 December 17, 1987 )

If you have any further questions relating to this matter, please contact Mr. M. H. Holmes at (303) 480-6960.

Very truly yours,

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R. O. Williams, Jr.

Vice President Nuclear Operations R0W/SBH/imb' cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain i

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