ML17324A720

Forwards Proprietary Responses to NRC 860108 Questions 6,8 & 10 Re XN-NF-85-64(P) & Rev 1 to XN-NF-85-64(P), Plant Transient Analysis for DC Cook Unit 2 W/10% Steam Generator Tube.... Encls Withheld (Ref 10CFR2.790(b))

ML17324A720
Person / Time
Site:	Cook
Issue date:	03/14/1986
From:	Copeland R SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17324A721	List: ML17324A720
References
RAC:022:86, RAC:22:86, NUDOCS 8603180242
Download: ML17324A720 (6)

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FACIL: 50-316 Donald C. Cook Nuclear Power Plant> Unit 2> Indiana 0 05000316 AUTH. NAME AUTHOR AFFILIATION COPELAND> R. A. Exxon Nuclear Co. > Inc. (subs. of Exxon Corp. )

RECIP. NAME RECIPIENT AFFILIATION DENTON> H. R. Of fice of Nuclear Reactor Regulation> Director (post 851125

SUBJECT:

Forwards proprietary responses to NRC 860108 Questions 6> 8 5 10 re XN-NF-85-64(P) 5 Rev 1 to XN-NF-85-64(P) > "Plant Transient" Analysis for DC Cook Unit 2 N/10/ Stean1 Generator Tube.... Encls withheld (ref 10CFR2. 790(b) ).

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DISTRIBUTION CODE: PA01D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: Proprietary Review Distribution-Operating Reactor RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PNR-A PD4 PD 05 5 5 INTERNAL'. ELD/HDS3 1 0 EG FILE RGN3 1 1 EXTERNAL: 24X 1 0 LPDR 1 0 NRC PDR 1 0 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 7

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2101 HORN RAPIO8 ROAO. PO BOX 130. RICKLANO,V/A99352 (5091 375-8100 TELEX: 15-2878 Narch 14, 1986 RAC:022:86 Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74 TRANSMITTAL OF PLANT TRANSIENT ANALYSES RESULTS IN SUPPORT OF UNIT 2 OPERATION Nr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Transmittal of Supplemental Plant Transient Analyses and Responses to NRC guestions Ref.: (1) XN-NF-85-64(P), "Plant Transient Analysis for D.C. Cook Unit 2 with 10% Steam Generator Tube Plugging," Exxon Nuclear Company, November 1985 (2) Letter, R.A. Copeland (ENC) to H.R. Denton (NRC), Harch 5, 1986; RAC:017:86 (3) XN-NF-85-64(Pf, Rev. 1, "Plant Transient Analysis for D.C.

Cook Unit 2 w>th 10% Steam Generator Tube Plugging," Exxon Nuclear Company, Narch 1986 (4) Letter, R.A. Copeland (ENC) to H.R. Denton (NRC), Novem-ber 15, 1985; RAC:070:85 Enclosed are five copies of responses to Numbers 6, 8 and 10 of the NRC questions transmitted January 8, 1986 to American Electric Power Service Corporation (AEPSC) concerning the Reference 1 topical report. This topical report provides support for Cycle 6 operation of the D.C. Cook Unit 2 nuclear power plant. Responses to guestions 1 through 4, 7, and ll were submitted by the Reference 2 letter.

between the NRC and AEPSC, the response As previously discussed to guestion 10 is a schedule to perform the requested additional analyses. As discussed in the Harch 13, 1986 telephone conversation between AEPSC, NRC and ENC personnel, the responses to the remaining questions, Numbers 5 and 9, will be transmit-ted as a separate submittal, later. This split submittal is intended, to permit the review to continue in a timely manner.

Also enclosed are five copies of the revised plant transient analysis report, Reference 3. This revision has three significant changes:

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l. A discussion is added to Subsection 15.0.2 to support a 7.5 psi increase in the pressurizer pressure uncertainty allowance.

2. The analysis results for event 15.4.1, Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condi-tion, have been replaced by results of new analyses using more conservative biasing of the delayed neutron fraction.

3. The results of event 15.4.6, Chemical and Volume Control System Halfunction that Results in a Decrease in Boron Concentration in the Reactor Coolant, have been deleted in this revision. The results of the analysis of this event will be provided in a supplement to Reference 3. The analysis is currently being reviewed by AEPSC.

At the request of AEPSC, these responses and topical reports are being transmitted directly to the NRC by Exxon Nuclear. Information contained in the responses is proprietary to the Exxon Nuclear Company. The Affidavit provided with the Reference 4 letter provides the necessary information to allow the withholding of the responses from public disclo-sure as required by 10 CFR 2.790(b).

If you have any questions regarding this transmittal, please contact Hr.

James G. Feinstein of AEPSC at (614) 233-2040.

Sincerely, R. A. Copeland Reload Licensing gf Enclosures cc: Hr. D. L. Wigginton (NRC)(w/encl.)

Hr. W. Jensen (NRC)(w/encl.)

Hr. H. P. Alexich (AEPSC)

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