ML17333A831

Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted

ML17333A831
Person / Time
Site:	Cook
Issue date:	03/26/1997
From:	Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A832	List: ML17333A831 ML17333A833
References
AEP:NRC:0433P, AEP:NRC:433P, NUDOCS 9704010331
Download: ML17333A831 (10)

Text

CATEGORY REGULAT INFORMATION DISTRIBUTIO STEM (RIDS)

';6 ACCESSION NBR:9704010331 DOC.DATE: 97/03/26 NOTARIZED: YES DOCKET SCIL:50-,315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315

, 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH; NAME AUTHOR AFFILIATION FITZPATRICK,E. American Electric Power Co., Inc.

FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to licenses DPR-58 & DPR-74,changing grammatical correction to wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & returning frequency requirement to TS 4.7.1.2.c & 4.7.1.2.d that was inadvertently deleted.

DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR i ENCL l SIZE: t 4 I t TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 HICKMAN,J 1 1 INTERNA .-'F E-GENTER 1 1 1 NRR/DE/ECGB/A 1 1

~/EMe 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

E NOTE TO ALL "RIDS" RECIPIENTS:

,PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

~4

~

f~

~ ~

Indiana Michigan Power Company

~

~

500 Circle Orive Buchanan, Ml 491071395 R

NfOIANSl MICNISARf POND March 26, 1997 AEP:NRC:0433P Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 ADMINISTRATIVE CORRECTIONS TECHNICAL SPECIFICATION CHANGE REQUEST This letter and its attachments constitute an application for amendment of the technical specifications (T/S) for Cook Nuclear Plant units 1 and 2. Specifically, we are proposing three administrative changes. The first change, "A", involves a grammatical correction to the wording of unit 2 T/S 3.4.8, ACTION

a. for MODES 1, 2, and 3. The second change, "B", returns a frequency requirement to T/S 4.7.1.2.c and 4.7.1.2.d that was inadvertently deleted in a prior amendment, and reformats the page to clarify the specified requirements. The third change, "C",

deletes a footnote to T/S 3.9.12 as it is no longer applicable.

Attachment 1 to this letter provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment 3 contains the proposed T/S pages.

We believe the proposed changes will not result in: (1) a significant change in the types of any effluent that may be released offsite; or (2) a significant increase in individual or cumulative occupational radiation exposure.

These proposed changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee.

In compliance with the requirements of 10 CFR 50.91 (b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and Michigan Department of Public Health.

SWORN TO AND SUBSCRIBED BEFORE ME S +~ DAY OF 1997 E. E. Fitzpatrick Notary Pub ic Vice President ommissiom Expires: WD~d

/jen lllttlll'jllll)tjllllllllllLlllllllllllllllll Attachments . 'Im ss 4ANICE Iti. BICI<ERS

,97040i0331 970326

'ADQCK 050003%5 Ii~Pu>c, tP/Qomrl'he BeNien Couniy ),ii s*

PDR on Exp es Feb 16 2001 P PDR

~ ~ ~

~ 4~

"e

%g C

3 ~

\

0

U. S. Nuclear Regulatory Commission AEP: NRC: 0433P Page 2 cc: A. A. Blind A. B. Beach MDEQ - DW 6 RPD NRC Resident Inspector Z. R. Padgett

ATTACHMENT 1 TO AEP:NRC:0433P DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS to AEP:NRC:0433P Page 1 I. DESCRIPTION OF CHANGES The proposed amendment to technical specification (T/S) 3.4.8, ACTION "a." for MODES 1, 2, and 3 makes the following change to Cook Nuclear Plant unit 2 T/S.

The word "for" is changed to read "or", as noted:

"...during one continuous time interval or exceeding the limit line shown..."

B. The proposed amendment to T/S 4.7.1.2.c makes the following addition to Cook Nuclear Plant units 1 and 2 T/ST "By verifying at least once per 31 days that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position."

The proposed amendment to T/S 4.7.1.2.d makes the following addition to Cook Nuclear Plant units 1 and 2 T/S.

. "By verifying at least once per 31 days that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER..."

Additionally, for further clarification, the phrase "when tested pursuant to Specification 4.0.5 by" is removed from the initial 4.7.1.2 statement, and added to paragraphs a and b, to which it specifically applies. Paragraph 4.7.1.2.a now reads:

"When tested pursuant to Specification 4.0.5 by verifying that each motor driven auxiliary feed pump's developed head at the test flow point is greater than or equal to the required developed head."

Paragraph 4.7.1.2.b now reads:

"When tested pursuant to Specification 4.0.5 by verifying that the turbine driven auxiliary feedwater pump's developed head when the secondary steam supply pressure is greater than 310 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3."

Paragraphs 4.7.1.2.e through g, have the word "By" inserted at, the beginning of the statement.

The proposed amendment to T/S 3.9.12 deletes footnote "+"

from Cook Nuclear Plant units 1 and 2 T/S:

+ "This does not include the main load block. For purposes of this specif ication, a deenergized main load block need not be considered a load."

~

'ttachment 1 to AEP:NRC:0433P Page 2 II. JUSTIFICATION FOR CHANGES A. The proposed revision corrects a typographical error. The unit 1 T/S contains the correct wording.

Prior to T/S amendments 164 and 149 to the units 1 and 2 T/Ss, T/S 4.7.1.2 required that each auxiliary feedwater pump be demonstrated operable at least once per 31 days. This included testing of the pumps, and verification of the proper alignment of the automatic and non-automatic valves in the auxiliary feedwater flow path". In a letter dated August 7, 1990, we requested an amendment to T/S 4.7.1.2 to delete the phrase "at least once per 31 days by:" and add the phrase "when tested pursuant to specification 4.0.5 by:".

This would then allow quarterly testing of the pumps, which would make the T/S more consistent with ASME code requirements. This request was found to be acceptable in a letter from the NRC dated April 22, 1992, which issued amendments 164 and 149.

In addition to the content changes made via these amendments, the page containing this new information was reformatted.

When the page was reformatted, the requirement to verify the position of the automatic and non-automatic valves at least once every 31 days was inadvertently deleted. As currently written, T/S 4.7.1.2.c and 4.7.1.2.d do not specify a frequency requirement. Additionally, as reformatted, not clear the phrase "when tested pursuant to Specification it was 4.0.5 by" was applicable to all paragraphs listed, not just

a. and b.

In spite of the fact there is no frequency specified in T/S

4. 7. 1.2. c and d, the automatic and non-automatic valve verifications have continued to be performed on a 31-day frequency.

T/S 3.9.7 prohibits loads in excess of 2500 pounds from being carried over fuel assemblies in the spent fuel pcol, and T/S 3 ~.12 prohibits crane operation with loads over the spent fuel pool with no fuel storage pool exhaust ventilation system operable. A previous footnote to T/S 3.9.7 was added, via amendments 93/79, to allow for movement of the main load block over the spent fuel pool while a load drop analysis was being performed. It was deleted, via amendments 113/96, when the load drop analysis was accepted by the NRC. A footnote to T/S 3.9. 12 was added, via amendments 124/111, to ensure consistency between 3.9.7 and 3.9.12. Because of overlapping amendments, the footnote added to T/S 3.9.12 was not deleted along with the T/S 3.9.7 footnote.

Subsequently, as part of the steam generator repair project in 1988, both the east and west auxiliary building cranes were designed under the provisions of NUREG-0554 to be single- failure-proof . PJREG-0612 section 5. 1. 2 exempts a single-failure-proof crane from the requirements of a load drop analysis. The main load blocks on the auxiliary building cranes, and the auxiliary hoist load block on the east crane, are now single-failure-proof blocks. As such, the load blocks are not considered to be heavy loads under the definitions of NUREG-0612, and may be carried over the spent fuel pool, unloaded (as stated in the UFSAR) . This footnote is, therefore, no longer applicable.

to AEP:NRC:0433P Page 3 III. 10 CFR 50.92 CRITERIA Per 10 CFR 50.92, proposed changes do not involve a significant hazards consideration if the changes do not:

1. involve a significant increase in the probability of consequences of an accident previously evaluated; create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. involve a significant reduction in a margin of safety.

Criterion 1 This amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed changes to the T/S do not affect the assumptions, parameters, or results of any UFSAR accident analysis. The first proposed change, "A", is a grammatical correction; the second proposed change, "B",

reformats the page, and returns a frequency requirement that, while inadvertently deleted from T/S, was still met via procedure; the third proposed change deletes a footnote which is no longer applicable. As described in section II.C.

above, a load drop analysis is not required for single-failure-proof load blocks.

Criterion 2 The proposed changes do not involve physical changes to the plant or changes in plant operating configuration. The changes described above are essentially administrative in nature, and thus do not create the possibility of a new or different kind of accident from any accident previously evaluated.

Criterion 3 The proposed changes are essentially administrative in nature. Per NUREG-0612, single-failure-proof cranes are exempt from the requirements of a load drop analysis; therefore, there is no significant reduction in the margin of safety.

ATTACHMENT 2 TO AEP:NRC:0433P CURRENT TECHNICAL SPECIFICATION PAGES MARKED-UP WITH PROPOSED CHANGES