ML17333B020

Responds to 970724 RAI Re 960711 5% Thermal Power Uprate Submittal AEP:NRC:1223

ML17333B020
Person / Time
Site:	Cook
Issue date:	08/27/1997
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1223F, NUDOCS 9709040278
Download: ML17333B020 (8)

Text

cZ CATEGORY 1 REGULATC INFORNATION DISTRIBUTION +TEM (RIDE)

ACCESSION 'NBR:9709040278 DOC.DATE: 97/08/27 NOTARIZED: YES DOCKET I FACIL:50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to 970724 RAI re 960711 5% thermal power uprate submittal AEP:NRC:1223.

DISTRIBUTION CODE: AOOZD TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution

/ENCL / SIZE:

NOTES:

RECIPIENT COPIES RECIPIENT COPIES E ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 1 HICKMAN,J 1 1 I 0

INTERN , ILg CENTE 1 1 1 NRR/DE/ECGB/A 1 1 NRR/DE/EMCB 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

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NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRIBUTION 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

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Indiana Michigan Power Company 500 Circle Drive Buchanan, Mi 491071395

à INDMMA NICHl6AM PQMfJFR August 27, 1997 AEP: NRC: 1223F tl Docket No.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Unit 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING POWER UPRATE AND RELATED CHANGES This letter and its attachment constitute a response to the July 24, 1997, NRC request for additional information regarding our July 11, 1996, 5% thermal power uprate submittal AEP:NRC:1223. The request for additional information primarily involves the impact of the uprating on the instrument set points.

This letter is submitted pursuant to 10 CFR 50.30(b) and, as such, includes an oath statement.

Sincerely, E. E. Fitzpatrick Vice President SWORN AND SUBSCRIBED BEFORE ME HIS 27th OF AUGUST 1997 jANEi'. OYKSlRA NOTARY PUBUC- BERRlEN COUN1Y, Ml JANET K. OY TRA N COMMSQON EXPiRES07/Ol/00 Notary ublic MY Commission Expires 07I701 SS vlb Attachment A. A. Blind A. B. Beach MDEQ " DW & RPD NRC Resident Inspector J. R. Padgett 970'F040278 970827 PDR ADQCK 050003l6 P PDR

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ATTACHMENT TO AEP:NRC:1223F REQUEST FOR ADDITIONAL INFORMATION REGARDING POWER UPRATE AND RELATED CHANGES RESPONSE

Attachment to AEP:NRC:1223F Page 1 NRC uestion "In order to assure that the revised instrument set points are well within the safety limits, please provide the following information for each changed instrument set point:

Part 1 "Change in the set point;"

Res onse to Part 1 Four instrument setpoint changes were proposed in the Cook Nuclear Plant unit 2 uprate submittal. These are OTDT, safety injection on pressurizer pressure low, safety injection on steam line pressure low, and steam line isolation on steam line pressure low. The submittal also includes a proposal to change the OPBT setpoint allowable value. The change for each setpoint is indicated in the following list as an ordered pair, with the current value first and the proposed value second for each setpoint, or in the case of OTbT, for each changed parameter or coefficient.

Maximum 576.0o F~ 581 3o F T'aximum 2235 psig, 2235 psig, or 2085 psig 1

P'au 28 secs, 22 secs Kl 1.09, 1.17 K2 0.01331, 0.0268 K3 0.00058, 0.00111 Low hI Break point -33~o, -16%

Low AI Penalty Slope 3 5%/%', 05+o/+o High hI Penalty Slope 1.0%'/%',

SI on pressurizer 2.7~a/%'900 pressure low psig, 1815 psig SI on steam line pressure low 600 psig, 500 psig Steam line isolation on steam line pressure low 600 psig, 500 psig I

Part 2 "Calculated worst case drift and page reference to the calculation that covers the drift including uncertainty calculation where applicable;"

Res onse to Part 2 When performing uncertainty calculations for setpoints, 2 drift terms are utilized: a drift term associated with the instrument sensor (transmitter, resistance temperature detector, etc.), and a drift term associated with the instrument rack.

For transmitter sensors, the drift term utilized in the uncertainty calculations is 1% of span and is considered a bounding value for the transmitters installed at Cook Nuclear Plant. This is the value that was used in the uncertainty calculations performed for the safety injection (SI) on pressurizer pressure low, SI on steam line pressure low, and steam line isolation on steam, line pressure low setpoints.

Attachment to AEP:NRC:1223F Page 2 To assure that the transmitters associated with the pressurizer pressure and steam line pressure instrument loops are bounded by the 1% drift term, a statistical analysis was performed on as-found/as-left calibration data that has been collected since the installation of the new Foxboro Spec 200 Protection System (Circa 1994) . The statistical analysis confirmed that the drift value for these transmitters is bounded by the 1% value utilized in the uncertainty calculations.

For the RTD sensors associated with the OPGT and OTAT setpoint uncertainty calculations, a drift term of 0.73' (or 0.72% of span) is utilized. This value has been provided by Westinghouse and is considered a bounding value.

The bounding value for the rack drift term is 1% of span. This value has been substantiated to be a bounding value for the instrument racks installed at Cook Nuclear Plant by Westinghouse.

mare S "Allowable value; and" Res onse to Part 3 The proposed changes in allowable values are indicated as ordered pairs with the current value first and the proposed value second for each setpoint in a format similar to that used to address item l.

OTLT 1.3% span, 3.75% span OPLT 3.0% span, 2.59% span SI on pressurizer pressure low 1890 psig, 1805 psig SI on steam line pressure low 585 psig, 480 psig Steam line isolation on steam line pressure low 585 psig, 480 psig Part 4 "Safety limit and page reference to the document that specifies the safety limit."

Res onse to Part 4 The safety limits are found in attachment 6 to our July 11, 1996, submittal. Attachment 6 is WCAP-14489. The page references to the safety limits in WCAP-14489 are as follows in a format similar to that used to address items 1 and 3.

Attachment to AEP:NRC:1223F Page 3 OTAT K1 = 1.37, Table 3.3-4, page 3.3-30 OPBT K4 = 1.17, Table 3.3-4, page 3.3-30 SI on pressurizer pressure low 1715 psia, Table 3.1-3, page 3.1-17 for LBLOCA*

1715 psia, Table 3.1-13, page 3.1-28 for SBLOCA*

1700 psig, Table 3.3-3, page 3.3-29 SI on steam line pressure low 344 psig, Table 3.3-3, page 3.3-29 Steam line isolation on steam line pxessure low 344 psig, Table 3.3-3, page 3.3-29**

• Values from RTSR Analysis Tables were used for all analyses.

• • Table 3.3-3 indicates "not applicable" for this function. It was confirmed with the Westinghouse analyst that this means the LOFTRAN model uses the same setpoint for safety injection and steam line isolation. Therefore, 344 psig is the correct value.

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