ML20137A467

From kanterella
Jump to navigation Jump to search

Forwards RAI Re DPC Proposed Amends for CNS to Eliminate from Plant TSs SIS on Low Steam Line Pressure
ML20137A467
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 03/18/1997
From: Tam P
NRC (Affiliation Not Assigned)
To: Mccollum W
DUKE POWER CO.
References
TAC-M97538, TAC-M97539, NUDOCS 9703200336
Download: ML20137A467 (4)


Text

_

r March 18, 1997 Mr. William R. McCollum Site Vice President Catawba Nuclear Station Duke Power Company 4800 Concord Road

~

York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION - PROPOSED TECHNICAL SPECIFICATION CHANGE TO ELIMINATE SAFETY INJECTION SIGNAL ON LOW STEAM PRESSURE (TAC M97538 ANd M97539)

Dear Mr. McCollum:

By letter dated January 3, 1997, Duke Power Company submitted proposed amendments for Catawba Nuclear Station to eliminate from the plant Technical i

Specifications the safety injection signal on low steam line pressure.

The staff has completed its initial review and determined that additional information, as identified in the enclosure, is needed.

We request that you provide the additional information within 45 day of your receipt of this letter.

If you or your staff need additional time to respond, or clarification of the questions, please contact me at 301-415-1451.

Sincerely, Original signed by:

Peter S. Tam, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosure:

Request for Additional Information cc w/ encl:

See next page EC E CM M C0Ff Distribution C.Casto,RII Docket File ACRS T-2 E26 PUBLIC OGC, 0-15 B18 PDII-2 RF J.Zwolinski

/j S.Varga S. Brewer, 0-8 E23 E.Merschoff,RII C. Liang, 0-8 E23 OFFICE DRPE/P022/SM,, _

DRPE/P022/LA DSSA/5RXB DSSA/SRXB/$C DRPE/ M 2/0 NAME P. Tam:en L. Berry

  • S. Brewer
  • M.Chatterton*

H.B r h/h/97 03 /14 /97 03 /17 /97 03 /17 /97 q /)797 DATE

-0FFICIAL RECORD COPY DOCUMENT 1AME:G:\\ CATAWBA \\ CAT 97538.RAI

  • See previous concurrence 9703200336 970318 PDR ADOCX 05000413 r

P pop

-.. -.. -.. - - - - - -. _,. - _ - - =

p Keroy p

UNITED STATES g

j NUCLEAR REGULATORY COMMISSION o

2 WASHINGTON, D.C. 20066 4 001

%..... [

March 18, 1997 Mr. William R. McCollum Site Vice President Catawba Nuclear Station Duke Power Company 4800 Concord Road York, South Carolina 29745-9635

SUBJECT:

CATAWBA NUCLEAR STATION - PROPOSED TECHNICAL SPECIFICATION CHANGE TO ELIMINATE SAFETY INJECTION SIGNAL ON LOW STEAM PRESSURE (TAC M97538 ANd M97539) l

Dear Mr. McCollum:

By letter dated January 3, 1997, Duke Power Company submitted proposed amendments for Catawba Nuclear Station to eliminate from the plant Technical Specifications the safety injection signal on low steam line pressure. The staff has completed its initial review and determined that additional information, as identified in the enclosure, is needed.

We request that you provide the additional information within 45 day of your receipt of this letter.

If you or your staff need additional time to respond, or clarification of the questions, please contact me at 301-415-1451.

Sincerely, A

Peter S. Tam, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosure:

Request for Additional Information cc w/ encl: See next page I

l

e Duke Power Company Catawba Nuclear Station cc

Mr. M. S. Kitlan North Carolina Electric Membership Regulatory Compliance Manager Corporation Duke Power Company P. O. Box 27306 4800 Concord Road Raleigh, North Carolina 27611 York, South Carolina 29745 Senior Resident Inspector Mr. Paul R. Newton 4830 Concord Road Legal Department (PB05E)

York, South Carolina 29745 Duke Power Company 422 South Church Street Regional Administrator, Region II Charlotte, North Carolina 28242-0001 U. S. Nuclear Regulatory Commission i

101 Marietta Street, NW. Suite 2900 J. Michael McGarry, III, Esquire Atlanta, Georgia 30323 Winston and Strawn 1400 L Street, NW Max Batavia, Chief Washington, DC 20005 Bureau of Radiological Health South Carolina Department of i

North Carolina Municipal Power Health and Environmental Control Agency Number 1 2600 Bull Street l

1427 Meadowwood Boulevard Columbia, South Carolina 29201 P. O. Box 29513 Raleigh, North Carolina 27626-0513 Mr. G. A. Copp 4

Licensing - EC050 Mr. Peter R. Harden, IV Duke Power Company Account Sales Manager 526 South Church Street Westinghouse Electric Corporation Charlotte, North Carolina 28242-0001 Power Systems Field Sales P. O. Box 7288 Saluda River Electric Charlotte, North Carolina 28241 P. O. Box 929 Laurens, South Carolina 29360 County Manager of York County York County Courthouse Ms. Karen E. Long York, South Carolina 29745 Assistant Attorney General North Carolina Department of Justice Richard P. Wilson, Esquire P. O. Box 629 Assistant Attorney General Raleigh, North Carolina 27602 South Carolina Attorney General's Office Elaine Wathen, Lead REP Planner P. O. Box 11549 Division of Emergency Management Columbia, South Carolina 29211 116 West Jones Street Raleigh, North Carolina 27603-1335 Piedmont Municipal Power Agency 121 Village Drive Dayne H. Brown, Director Greer, South Carolina 29651 Division of Radiation Protection N.C. Department of Environment, Mr. T. Richard Puryear Health and Natural Resources Owners Group (NCEMC)

P. O. Boz 27687 Duke Power Company Raleigh, North Carolina 27611-7687 4800 Concord Road York, South Carolina 29745

1 REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA NUCLEAR STATION UNITS 1 AND 2 j

AMENDMENT TO ELIMINATE THE SAFETY INJECTION SIGNAL ON LOW STEAM PRESSURE

{

t f

Reference:

Letter, M. S. Tuckman to NRC, January 3, 1997.

l 1.

Does the removal of the low steam pressure safety injection (SI) i signal impact the emergency operating procedures? If so, please explain.

l 2.

It is the staff's understanding that by removing the low steam pressure j

safety injection signal, you intend to prevent an SI actuation following a loss of offsite power event. How have you ensured that the resultant 1

change in the SI actuation could effectively suppress an unnecessary SI

~

actuation in this case?

h 3.

Discuss your plan to take corrective actions on the design deficiency in the main steam system to prevent the potential excess reactor coolant system cooldown following a loss of offsite power event. The aroposed plant configuration could lead to a transient different from t1e event analyzed in Final Safety Analysis Report.

4.

What spectrum of break sizes was evaluated for the main steamline break transient with the removal of low steam pressure safety injection signal? Please provide detailed results of your evaluation.

5.

You stated in your submittal that a small steamline break causes the SI to actuate on low pressurizer pressure before reaching the setpoint of the low steam pressure safety injection signal. At what break size does the SI actuation switch from low pressurizer pressure to low steam pressure?

6.

Provide the results of the reanalized steamline break transient without SI initiated from low steam pressure.

Include the sequence of events and the major transient curves (nuclear power, pressure, temperature, DNBR,etc.).

Enclosure