ML20207J180

Forwards follow-up Items Re Proposed Conversion to Improved Tech Specs Section 1.0,3.1,3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0.Suppl to Ltr Dtd 970515,provided Current with Ltr

ML20207J180
Person / Time
Site:	Wolf Creek
Issue date:	03/05/1999
From:	Muench R WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20207J185	List: ML20207J180 ML20207J202
References
ET-99-0010, ET-99-10, NUDOCS 9903160209
Download: ML20207J180 (9)

Text

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W@ NUCLEAR LF CREEK OPERATING Richard A. Muonch Vice President Engineenng MAR 5 1999 ET 99-0010 U. S. Nuclean Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, D. C. 20555

Reference:

1) Letter ET 97-0050. deced May 15, 1997, from R. A.

Muench, WCNOC, to'USNRC

2) Letter ET 98-00049, dated June 30, 1998, from R. A.

Muench, WCNOC, to USNRC

3) Letter WO 98-0078,- dated August 5, 1998, from C. C. i Warren, WCNOC, to USNRC

4) Letter ET 98-0072, dated August 28, 1998, from R. A.

Muench, WCNOC. to USNRC

5) Letter ET 98-0078, dated September 24, 1998, from R. A.

Muench, WCNOC,'to UENRC 6)' Letter ET 98-0085, dated October 16, 1998, from R. A.

Muench, WCNOC, to USNRC i

- 7) Letter ET 98-0087, dated October 23, 1998, from R. A. l Muench, WCNOC, to USNRC '

8) Letter WO 98-0105, dated November 24, 1998, from C. C.

Warren, WCNOC, to USNRC

9) Letter ET 98-0098, dated December 2, 1998, from R. A.

Muench, WCNOC, to USNRC

10) Letter ET 98-0102, dated December 17, 1998 from R. A.

Muench, WCNOC to USNRC

11) Letter ET 98-0107, dated December 21, 1998, from R. A.

Muench, WCNOC, to USNRC

12) Letter ET 99-0004, dated February 4, 1999, from R. A.

Muench, WCNOC, to USNRC Sub]ect: Docket No. 50-482: Follow-up Items Related to the Proposed Conversion to the Improved Technical Specifications Section 1.0, 3.1, 3.2, 3.3, 3.4, 3.6, 3.7, 3.8, 3. 9, 4.0 and 5.0 Gentlemen:

Wolf Creek Nuclear' Operating Corporation (WCNOC) requested an amendment te the Wolf Creek. Generating Station (WCGS) Unit 1 facility operating lictnse (NPF-

42) by incorporating changes to the WCGS Technical Specificationa (7S) as provided in Reference 1. The NRC staff z. quested additional information regarding Section 3.6, " Containment Systems," which was provided in Reference

2. The NRC staff requested additional information regarding Section 3.1,

" Reactivity ' Control Systems," Section 3.2, " Power Distribution Systems,"

Section 3.5, ~" Emergency Core Cooling Systems," Section 3. 9, " Refueling Operations," and 4.0, " Design Features," which was provided in Reference 3.

The NRC staff requested additional information regarding Section 1.0, "Use and Application," Section 2. 0, " Safety Limits," and Section 3.0, " Limiting 0g Conditions for Operation Applicabi 4ty/ Surveillance Requirement Applicability" hg3 which was provided in. Reference 4. The NRC staff requerted additional \

information regarding Section 3.4, " Reactor Coolant System," and Section 5.0,

" Administrative Controls," which was provided in Reference 5. The NRC staff 9903160209 990305 PDR p ADOCK 05000482 i, KS 66839 / Phone: (316) 364-8831 PDR ,

an tyue vpportunity Employer M THCVET b'

4-

.- ET 99-0010

.Page.2-

.requer:ted additional information regarding Section 3.7, " Plant Systems," which was provided in Reference.6. The NRC staff requested additional information

>regarding Section.3.3, " Instrumentation," which was provided in Reference 9.

'The NRC ' staff requested additional information regarding Section 3.8, 3 "Electrica' DoW r Systems," which was provided in Reference 10.

The Attachments to lthis letter provide (1) additional information or supporting documentation not provided in the original Request for Additional

Information' response,- (2) answers to follow-up questions, or (3) additional changes -identified by: tine licensee. Reference 7 provided the first follow-up letter, ' affecting ITS Sections 3.1, 3.2, 3.4, 3.5, and 5.0. Reference 8 providedithe second follow-up letter, affecting ITS Sect.ons 1.0, 3.4, 3.5, and 3.6. Reference 11 provide.d the third follow-up letter, affecting ITS Sections 1.0, 3.1, 3.2, 3.3, 3.4, 3.7, 3.9, and 5.0. Reference 12 provided the fourth follow-up letter, affecting ITS Sections 1.0, 3.2, 3.3, 3.4, 3. 6, 3.7,3.8,.3.9 and 5.0.

This letter and : Enclosure are not a supplement to Reference 1 and hive not been reviewed by the Plant Safety Review Committee or Nuclear Safety Review LCommittee. A supplement to Reference 1 is provided current with this lett(r.

-Iflyou have any questions concerning this response, please contact me at (316) 364-4034, or Mr. Michael J. Angus, 316-354-4077.

Very truly yours, MA Richa A. Muench

. Attachmerits Enclosure

' RAM /rir-cc: W. D. Johnron(NRC), w/a E. W. Merschoff (NRC), w/a

""mior Resident Inspector (NRC), w/a K. M. Thomas (NRC), w/a E

r

STATE OF KANSAS )

) ss COUNTY OF COFFEY )

I Richard A. Muench, of lawful age, being first duly sworn upon oath says that 3 he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; l that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By (

Richard . Muench Vice Pr ident Engineering SUBSCRIBED and sworn to before me this day of [7fd/)6 , 1999.

M Gnt/n k No'ary Public 2dnO48n t ~ ~ ([

urm wC-IMono Expiration Date M //- [/)/)2 i

l t_ _

I: I i Attichment 1 to ET 99-0010 Page 1 of 3

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l The item numbers are formatted as follows: [ Source} [lTS Section]-[nnn]

Source = Q - NRC Question i NR - NRC Follow-up Question CA - AmerenUE DC-PG&E WC-WCNOC CP - TU Electric TR - Traveler l ITS item Numben- Applicability Enclosed 1.0 Q 1.1-1 TSTF-205 WC YES l

3.1 WC 3.1-001 (new) WC YES l 3.2 WC 3.2-002 (new) WC YES 3.3 Q 3-LS-GEN WC YES

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3.3 Q 2-02 (3.3) CA, WC YES 3.3 O 2-18 CA, WC YES l 3.3 O 2-37 WC YES 3.3 O 3-01 WC YES 3.3 Q 7-13 CA,WC YES 3.3 Q 3.3-04 CA NA 3.3 Q 3.3-21 CA,WC YES 3.3 Q 3.3-30 WC YES 3.3 0 3.3-32 CA, WC YES 3.3 Q 3.3-34 CA, WC, DC YES 3.3 Q 3.3-55 CA, WC YES 3.3 0 3.3-80 CA,WC YES  :

3.3 Q 3.3-99 CA, WC YES 3.3 Q 3.3-135 CA, WC YES 3.3 CA 3.3-024 (new) CA NA 3.3 CA 3.3-025 (new) CA NA 3.3 TR 3.3-007 DC NA 3.3 WC 3.3-020 (new) WC YES 3.3 WC 3.3-021 (new) WC YES 3.3 WC 3.3-022 (new) WC, CA YES I 1.3 WC 3.3-023 (new) WC YES 3.3 WC 3.3-024 (new) WC YES i 3.4 0 3.4.11-2, TSTF-288 CA, DC, WC YES 3.4 O 3.4.11-3, TSTF-113 CA, WC YES 3.4 WC 3.4-011 WC YES j

I Attrchm:nt 1 to ET 99-0010 Page 2 of 3 3.6 Q 3.6.1-6 DC,CA NA 3.6 O 3.6.3-1 WC YES 3.6 O 3.6.3-4 CA NA

! 3.6 O 3.6.3-10 CA NA i 3.6 Q 3.6.3-11 WC YES

! 3.6 Q 3.6.3-17 CA CA l l 3.6 Q 3.6.3-23 CA, WC YES l 3.6 Q 3.6.3-33 CA NA 3.6 Q 3.6.6-8 DC NA l

3.7 Q 3.7.16-3 CA, WC YES 3.7 Q 3.7.17.1-6 CA, WC YES i 3.7 CA o' .7-005 CA NA 3.7 CA 3.7-010 (naw) CA NA 3.7 CA 3.7-011 (new) CA NA

! 3.7 WC 3.7-009 (new) WC YES l 3.7 WC 3.7-101 (new) WC YES i l

! 3.8 Q 3.8.1-09CW CA NA 1 3.8 Q 3.8.1-12DC DC NA 3.8 Q 3.8.1-12WC WC YES 3.8 Q 3.8.1-15WC WC YES 3.8 Q 3.8.1-18DC DC NA 3.8 Q 3.8.1-27DC DC NA 3.8 Q 3.8.1-29DC DC NA l

3.8 Q 3.8.1-33DC DC NA _

l 3.8 Q 3.8.2-04CW CA NA l 3.8 O 3.8.3-06DC DC NA 3.8 O 3.8.4-08 \'!C YES 3.8 O 3.8.4-10 C:\ NA 3.8 O 3.8.4-17 WC YES 3.8 Q 3.8.4-18 CA NA l 3.8 Q 3.8.4-29 WC YES 3.8 Q 3.8.B-01.a CA NA 3.8 Q 3.8.B-01.g CA NA 3.8 Q 3.8.B-01j CA NA 3.8 Q 3.8.B-01p CA NA 3.8 Q 3.8.B-04.r WC YES 3.8 CA 3.8-003 (new) CA NA 3.8 DC 3.8-ED DC NA 3.8 WC 3.8-007 (new) WC, CA YES

I Att:chment 1 to ET 09-0010 Pcge 3 of 3 3.9 WC 3.9-007 (new) WC, CA, DC YES 4.0 WC 4.0-ED (new) WC YES I

5.0 Q 5.2-1 CA NA 5.0 WC 5.0-007 (new) WC YES l

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ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-1 APPLICABILITY: WC REQUEST: CTS 1.3, Analog Channel Operations Test CTS 1.3, Channel Operational Test (Diablo Canyon)

CTS 1.7, Channel Functional Test [Diablo Canyon)  ;

CTS 1.35, Trip Actuating Device Operational Test (Wolf Creek)

CTS 1.36, Trip Actuating Device Operational Test [Callaway)

CTS 1.37, Trip Actuating Device Operational Test [ Comanche Peak)

CTS 1.38, Trip Actuating Device Operational Test (Diablo Canyon)

DOC 1-30-A ITS 1.1, Channel Operational Test (COT)

ITS 1.1, Channel Functional Test (CFT) [Diablo Canyon)

ITS 1.1, Trip Actuating Device Operational Test (TADOT)

JFD 1.1-9 These are changes to both the CTS and the STS and are considered generi .

Therefore, they are beyond the scope of the conversion review. The DOC states that these changes are consistent with TSTF-39, Rev.1. Also, Diablo Canyon's ITS markup appears to be in error as shown by " Channel Operational" versus " Channel Operational Test (COT)."

Comment: If NRC has not approved TSTF-39 by the time the draft safety evaluation is prepared, then these changes should be withdrawn from the conversion submittal at that time. These changes will not be reviewed on a plant-specific basis. In addition, correct the Diablo Canyon ITS markup for COT.

FLOG RESPONSE: (original) TSTF-39 Rev.1 has been withdrawn by the TSTF. However, changes addressed in TSTF-39 Rev.1 have been subsumed by TSTF- 1 205. Revision 1 of TSTF-205 is currently undergoing final review by the .

TSTF members. After final wording changes for the COT definition as I well as Section 3.3 Bases changes to establish the requirements for relay contact surveillance testing (issue originally raised at Peach Bottom) are agreed upon, Revision 1 will be submitted for NRC review. The attached i pages represent the definition changes to be included in Revision 1. The Section 3.3 Bases changes will be addressed under that Section's review.

FLOG RESPONSE: (supplement) The FLOG proposes to incorporate Revision 3 of TSTF-205 which has been approved by NRC. The only changes required involve the definitions of MASTER RELAY TEST and SLAVE RELAY TEST. ITS Section 3.3 Bases changes to relax the requirements for relay contact surveil.ance testing, which per the traveler may be performed during COTS and TADOTs by the verification of the change of state of a single contact of the relay, have not been incorporated.

FLOG RESPONSE: (supplement) During final safety committee reviews, it was identified that the Wolf Creek revision did not accurately reflect TSTF-205, Rev. 3. The changes to the attached pages are consistent with TSTF-205, Rev. 3.

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l ATTACHED PA2ES:

Attachment No. 4, CTS 1.0 - ITS 1.0 l Encl. 2 1-1 Encl.5A 1.1 -1, 1.1 -2, 1.1-6 1 l

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