ML20147B561

Requests Addl Info Re Generic Ltr 86-06, Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps.' Response Needed within 60 Days of Ltr Date

ML20147B561
Person / Time
Site:	Calvert Cliffs
Issue date:	02/24/1988
From:	Mcneil S Office of Nuclear Reactor Regulation
To:	Tiernan J BALTIMORE GAS & ELECTRIC CO.
References
TASK-2.K.3.05, TASK-TM GL-86-06, GL-86-6, TAC-49674, TAC-49675, NUDOCS 8803020121
Download: ML20147B561 (4)

Text

5 February 24, 1988 Docket Nos. 50-317 DISTRIRlITION and 50-318 5555W9fW- CVogan i

PDI-1 RDG, SMcNeil NRCPDR OGC Local PDR EJordan SVarga JPartlow

' Mr. J. A. Tiernan BBoger ACRS(10)

Vice President-Nuclear Energy LTripp SWu Baltimore Gas and Electric Company P.O. Box 1475 Baltimore, Maryland 21203

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 86-06 "IMPLEMENTATION OF TMI ACTION ITEM II.K.3.5, ' AUTOMATIC TRIP OF REACTOR COOLANT PUMPS'" (TACS 49674 AND 49675)

The NRC staff contractor, ?G&G Idaho,- Inc., has conpleted its initial review of your letters dated Octot,ir 23 and November 21, 1986. These submittals were provided in response tu NRC Generic Letter 86-06.- It has been determined that additional information is required to complete this review. The request for additioral information is enclosed.

Please provide the information as reauested within 60 days following the l issuance of this letter. If additional time is needed to provide the  !

requested infomation, please inform us of your proposed schedule for providing this information within 30 days of the issuance date.

When jou respond to this request, please include our technical assignment control -

numbers (TACS 49674 and 49675) in your subject line. Including these numbers i permits superior trackino of all correspondence related to this specific issue in the NRC's computerized internal tracking system (NUDOCS) which also is 4 available for public use at the NRC's Public Document Room.

The reporting and/or recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OM3 clearance is not required under PL 96-511. ,

Sincerely, i l

p Scott Alexander McNeil. Project Manager O$o3020d pR P

$ $$ Project Directorate I-1 Division of Reactor Projects I/II  ;

Enclosure:

As stated l 1

cr : See next page l

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Mr. J. A. Tiernan Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant ec:

Mr. .lohn M. Gott, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Comission Comissioners 475 Allendale Road Prince Frederick, Maryland 20768 King of Prussia, Pennsylvania 19405 D. A. Brune, Esq.

General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant

usb Ma y and b6 -007 Pesident Inspector

. c/o U.S. Nuclear Regulatory Commission '

P. O. Box 437 l.usby, Maryland 20657-0073 Bechtel Power Corporation ATTN: Mr. D. E. Stewart Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Marylard 20760 Combustion Engineerino, Inc.

ATTN: Mr. W. R. Horlacher, III Project Manager

P. O. Box 500 i 1000 Prospect Hill Road  !

Windsor, Connecticut 06095-0500 l l

Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN: Mr. T. Magette Tawes State Office Building Annapolis, Maryland 21904

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RE00EST FOR ADDITIONAL INF0FMATION BALTIMORE GAS A ELECTRIC COMPANY CALVERT CLIFFS NtlCLEAR POWER PLANT UNITS 1 AND ?,

DOCKET NOS. 50-317 AND 50-318 RESPONSE TO GENERIC LETTER 86-06 "IMPLEMENTATl0NOFTMIACTIONITEMII.K.3.5"

1. The licensee's description (ref.1) of the instrumentation uncertainties for loop PT-105 differs from the material presented in previous letters (ref. 2, 3). The licensee intends to use an uncertainty of approximately P.12 psia during the first F minutes of a LOCA or non-LOCA transient.

> After 5 minutes have passed an uncertainty of 4?3 psia will be used. The licensee needs to describe the basis for determining the 21? and 473 psia uncertainties for 1000 PT-105. Also, the licensee needs to describe how the 5 minute switch point was determined.

2. The generic responses to Questions 48-55 (ref. 51 describe the maior assumptions used in the CE .nalyses. The licensee needs to review these assumptions and verify that they are valid for Calvert Cliff;. The ,

licensee's response can be presented as a corresponding list of plant specific values, noting areas of conservatism. Any plant specific values

, that are less censervative than the generic analyses must be justified.

3. Section 5 of CEN-268 (ref. 4) evaluates sample transients that are i representative of CE plants. The generic setpoints (1300 psia primary 4

pressure and 20*F subcooling margin) and the predicted system behavior ,

were discussed. The licensee needs to verify that the plant specific l setpoints will not significantly affect the results of the generic

, analyses,

a. Verify that the generic assessment of each transient is valid for Calvert Cliffs, i.e., the time at which the Calvert Cliffs pumps are tripped (1725 psia setpoint plus uncertainty) is not significantly different from the tire when the pumps are tripped for the generic case. The licensee can ext,ress this assessment in terms of the appropriate transient curves, primary and secondary setpoints including uncertainty, system behavior, and availability of equipment (e.g., use of more than 1 HPSI or nake up pump during recovery from the t*ansient).

b. If the Calvert Cli'fs assessment in (a) leads to different results than the generic roport, (e.g., trip all 4 pumos at Calvert Cliffs instead of triopinil 2 pumps and leaving ? pumps running, then describe the basis for acceptance. The licensee should be mindful of meeting the intent of Genvric Letter 86-06, namely "pumps will remain running

for those non-L0r A transients and accidents where forced convection j cooling and prersurizer pressure control would enhance plant control."

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4. The licensee indicated (ref.1) that implementation of the RCP trip strategy is consistent with the CE Report NPS0-151-P "CE Safety Analysis Methods for Calvert Cliffs Units 1 and 2." The licensee is requested to provide an information copy of this document.

REFERENCES:

1. Telephone conference between BGSE, NRC, EG&G Idaho, Inc "Clarification of Calvert Cliffs Response to Generic Letter 86-06", November 30, 1987. i

2. Letter from J. A. Tiernan (BG&E) to A. C. Thadani (NRC), dated October 23, 1986.

3. Letter from J. A. Tiernan (BG&E) to A. C. Thadani (NRC), dated l

November 21, 1986.

4. Combustion Engineering Report CEN-268, dated March 1984

5. Combustion Engineering Report CEN-268 Supplement 1-NP, dated <

November 1904 l

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