ML17158B946

Forwards RAI Re Proposed TS Amend & Requests Response by End of Feb 1997

ML17158B946
Person / Time
Site:	Susquehanna
Issue date:	02/12/1997
From:	Poslusny C NRC (Affiliation Not Assigned)
To:	Byram R PENNSYLVANIA POWER & LIGHT CO.
References
TAC-M97167, NUDOCS 9702180335
Download: ML17158B946 (7)

Text

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~,Feb' 1.2, 1997 Mr. Robert G.

Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING PROPOSED TECHNICAL SPECIFICATION AMENDMENT FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, SECONDARY CONTAINMENT ISOLATION RADIATION MONITOR SETPOINTS (TAC NOS.

M97167 AND H97168)

Dear Hr. Byram:

The NRR technical staff have completed a review of the request for a modification to the Technical Specifications for Susquehanna Steam Electric Station, Units 1 and 2, dated October 7, 1996.

This request would change the setpoints for the secondary containment radiation monitors.

On the basis of this review, the staff has determined that it needs additional information to complete its evaluation of the license amendment.

Please provide a response to the enclosed RAI by the end of February 1997 to support our review schedule.

Sincerely,

/s/

Chester

Poslusny, Senior Project Manager Project Dir'ectorate I-2 Division-of Reactor Projects - I/II Office, of Nuclear Reactor Regulation Docket Nos.

50-387/388

Enclosure:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 February 12, 1997 Mr. Robert G. Byram Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

SUBJECT:

RE(VEST FOR ADDITIONAL INFORMATION (RAI) CONCERNING PROPOSED TECHNICAL SPECIFICATION AMENDMENT FOR SUS(UEMANNA STEAM ELECTRIC STATION, UNITS 1

AND 2, SECONDARY CONTAINMENT ISOLATION RADIATION MONITOR SETPOINTS (TAC NOS.

H97167 AND M97168)

Dear Mr. Byram:

The NRR technical staff have completed a review of the request for a modification to the Technical Specifications for Susquehanna Steam Electric Station, Units 1 and 2, dated October 7, 1996.

This request would change the setpoints for the secondary containment radiation monitors.

On the basis of this review, the staff has determined that it needs additional information to complete its evaluation of the license amendment.

Please provide a response to the enclosed RAI by the end of February 1997 to support our review schedule.

Sincerely,

,Docket Nos. 50-387/388

Enclosure:

As stated cc w/encl:

See next page Chester

Poslusny, Senior Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

t Mr. Robert G.

Byram Pennsylvania Power

& Light Company Susquehanna Steam Electric Station, Units 1

& 2 CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts

& Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. J.

H. Kenny Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. K. Jenison Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Mr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.

Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania

. 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. George Kuczynski Plant Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Chairman Board of Supervisors 738 East Third Street

Berwick, PA 18603

RE UEST FOR ADDITIONAL INFORNATIO EGARDING PENNSYLVANIA POWER AND LIGHT COMPANY'S OPOSED EC NICAL SPECIFICATION S

ENDMENT 0

SUS UEHANNA STEAN E CT C S TION UNI S I AND 2 SECOND RY CONTAINMENT ISOL IO DI IO 0 I OR SETPOINTS The proposed TS would revise the setpoints and allowable values of several secondary containment isolation radiation monitors.

The submittal dated October 7, 1996, describes the need for the changes.

However, it is not clear to the staff how the new values were determined.

The staff also needs justification addressing the acceptance of these new values.

Specifically, the staff requests the following information:

Provide information on mitigative actions that will be implemented to reduce the expected increase in dose to personnel in unrestricted

areas, that would result from the operation of Hydrogen Water Chemistry (HWC).

This should include estimates of the expected increase in the yearly dose rate (external gamma radiation) in unrestricted areas.

Also provide estimates of the increase in exposure levels of external radiation in and around the turbine building components.

2.

3.

5.

6.

7.

How does the expected increase in the yearly dose rate impact compliance with 10 CFR Part 20?

(Refer to specific reference to 40 CFR Part 190 in 10 CFR Part 20.)

Provide an estimate of the increasing number of High Radiological

Areas, locked High Radiological Areas, and the increase in person-rem per year, to occupational workers.

Describe changes planned for plant maintenance and surveillance work in and around affected areas in the turbine building and main steam tunnels.

Provide the data that was used to calculate the expected increase in dose

rates, resulting from the operation of HWC, at the site boundary.

This

. should also include the expected increase in dose at the site boundary.

'as a test of Hydrogen addition been performed?

If so, please provide the results of this test.

If no demonstration has been run, explain the basis for amendment request.

With the operation of HWC; what will be the effect on the operability.of-the radiation monitors for the Main Steam Line?

Have the setpoints to

'hese radiation monitors been increased to allow for HWC operation?

If so, please provide the data used to calculate these setpoints and the setpoint values.

ENCLOSURE

8.

On what basis were the new values of the secondary containment isolation radiation monitor setpoints and allowable values determined to be acceptable?

Mhat criteria were used for determining the acceptance?

How much has the margin been changed regarding Part 100 limits?

9.

Provide the justification for using the "[Final Safety Analysis Report]

FSAR realistic source terms" instead of the "worst case source terms" for accident conditions that require isolation of the secondary containment in the calculation of the revised setpoints?

10. Provide the quantitative calculations for the analytical limit which utilized FSAR realistic source terms.

The information provided should include the actual calculations and results.

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