ML17157C220

Forwards Request for Addl Info on Effects of Loss of Spent Fuel Pool Cooling Event Following LOCA

ML17157C220
Person / Time
Site:	Susquehanna
Issue date:	02/18/1993
From:	Clark R Office of Nuclear Reactor Regulation
To:	Keiser H PENNSYLVANIA POWER & LIGHT CO.
References
NUDOCS 9303030181
Download: ML17157C220 (7)

Text

':Docket Nos.

50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

Dear Mr. Keiser:

February 1

1993

SUBJECT:

RE(VEST FOR ADDITIONAL INFORMATION (RAI) ON THE EFFECTS OF LOSS OF SPENT FUEL POOL (SPF)

COOLING EVENT FOLLOWING A LOSS OF COOLANT

ACCIDENT, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NO. M85337)

The spent fuel pool (SFP) cooling systems for the Susquehanna Steam Electric Station (SSES),

Units 1 and 2, as described in the Updated Final Safety Analysis Report are non-seismic Category 1, non-Class 1E powered and guality Group C systems.

Therefore, loss of offsite power (LOOP) or a seismic event may render the SFP cooling systems inoperable.

Actions in response to this rely on operator entry to the pool area to manually add make-up water.

We are reviewing a

10 CFR Part 21 report on the above subject and have determined that we need the additional information identified in the enclosure to this letter to complete our evaluation.

Rather than requesting you to provide a written response to these questions at this time, we propose that the questions be used as the agenda for a meeting with your staff in the near future.

The meeting would be open to the public and any interested parties.

Please contact me so that a mutually agreeable date for such a meeting can be arranged.

Enclosure:

Request for Additional Information cc w/enclosure:

See next page DISTRIBUTION

'ocket File NRC S. Local PDRs PDI-2 Reading SVarga Jcalvq Oi0029 CMi 1 1 er RClark MO'Brien OGC ACRS(10)

EWenzinger, RGN-I

JWhite, RGN-I Sincerely, Original signed by'ichard J. Clark Richard J. Clark, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DShum LKokajko JEccleston OFFICE NAME P,DI MO'Brien PDI-RC

rb PDI-2 D

CMi DATE

/

93 dP //8/93

'/93 OFFICIAL RECORD COPY DOCUMENT NAME:

SU85337.RAI 9303030181 930218 PDR ADOCK 05000387, P,,

PDR

Docket Nos.

50-387 and 50-388 Hr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

Dear Hr. Keiser:

February 1993

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE EFFECTS OF LOSS OF SPENT FUEL POOL (SPF)

COOLING EVENT FOLLOWING A LOSS OF COOLANT ACCIDENT, SUSQUEHANNA STEAN ELECTRIC STATION, UNITS 1

AND 2 (TAC NO. M85337)

The spent fuel pool (SFP) cooling systems for the Susquehanna Steam Electric Station (SSES),

Units 1 and 2, as described in the Updated Final Safety Analysis Report are non-seismic Category 1, non-Class 1E powered and Quality Group C systems.

Therefore, loss of offsite power (LOOP) or a seismic event may render the SFP cooling systems inoperable.

Actions in response to this rely on operator entry to the pool area to manually add make-up water.

We are reviewing a

10 CFR Part 21 report on the above subject and have determined that we need the additional information identified in the enclosure to this letter to complete our evaluation.

Rather than requesting you to provide a written response to these questions at this time, we propose that the questions be used as the agenda for a meeting with your staff in the near future.

The meeting would be open to the public and any interested parties.

Please contact me so that a mutually agreeable date for such a meeting can be arranged.

Enclosure:

Request for Additional Information cc w/enclosure:

See next page

~OI TRIT Till Docket File NRC 8 Local PDRs PDI-2 Reading SVarga JCalvo CMiller RClark HO'Brien OGC ACRS(10)

EWenzinger, RGN-I JWhite RGN-I Sincerely, Original signed by Richard J. Clark Richard J. Clark, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation DShum LKokajko JEccleston OFFICE pd PDI-PDI-2 D

NAME DATE HO'Brien I/

93 RC:rb dP /le/93 CHi

/93 OFFICIAL RECORD COPY DOCUMENT NAME:

SU85337.RAI

~pg AEQ(p~

P O~C 0

C Vl O~

Cy

/yn

~O

~>>*<<~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566 February 18, 1993 Docket Nos.

50-387 and 50-388 Mr. Harold W. Keiser Senior Vice President-Nuclear Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE EFFECTS OF LOSS OF SPENT FUEL POOL (SPF)

COOLING EVENT FOLLOWING A LOSS OF COOLANT ACCIDENT, SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1

AND 2 (TAC NO. M85337)

The spent fuel pool (SFP) cooling systems for the Susquehanna Steam Electric Station (SSES),

Units 1 and 2, as described in the Updated Final Safety Analysis Report are non-seismic Category 1, non-Class 1E powered and guality Group C systems.

Therefore, loss of offsite power (LOOP) or a seismic event may render the SFP cooling systems inoperable.

Actions in response to this rely on operator entry to the pool area to manually add make-up water.

We are reviewing a

10 CFR Part 21 report on the above subject and have determined that we need the additional information identified in the enclosure to this letter to complete our evaluation.

Rather than requesting you to provide a written response to these questions at this time, we propose that the questions be used as the agenda for a meeting with your staff in the near future.

The meeting would be open to the public and any interested parties.

Please contact me so that a mutually agreeable date for such a meeting can be arranged.

Sincerely, e

Enclosure:

Request for Additional Information ard J.

ark, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosure:

See next page

Mr. Harold W. Keiser Pennsylvania Power

& Light Company Susquehanna Steam Electric Station, Units 1 5 2 CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts 5 Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Scott Barber Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.

Box 2063 Harrisburg, Pennsylvania 17120 Mr. 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. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,

Box 1797 Berwick, Pennsylvania 18603 Mr. Robert G.

Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. David A. Lochbaum 80 Tuttle Road

Watchung, New Jersey 07060 Mr. Donald C. Prevatte 7924 Woodsbluff Run Fogelsville, Pennsylvania 18051

ENCLOSURE RE VEST FOR ADDITIONAL INFORMATION EFFECTS OF LOSS OF SPENT FUEL POOL COOLING EVENT SUS UEHANNA STEAM ELECT C STATION UNITS 1

AND 2 DOCKET NOS.

50-387 AND 50-388 The spent fuel pool (SFP) cooling systems for the Susquehanna Steam Electric Station (SSES),

Units 1 and 2, as described in the Final Safety Analysis Report (FSAR) are non-seismic Category 1, non-Class IE powered and guality Group C systems.

Therefore, loss of offsite power (LOOP) or a seismic event may render the SFP cooling systems inoperable.

Actions in response to this rely on operator entry to the pool area to manually add make-up water.

Provide analyses and evaluations to address the radiological and environmental conditions that an operator will encounter.

This analysis should include an evaluation of the consequences for the loss of SFP cooling during the refueling outage with a full core off loaded in the SFP at one unit and a

LOCA at the other unit.

Include the following in the discussion:

1.

Discuss the total decay heat loads for the spent fuel pool in accordance with SRP 9. 1.3

( provide the input parameters to include: rated power of

reactor, number of fuel assemblies in the core, the number of fuel elements off loaded during the refueling operation, the time intervals between refuelings, the least time from shutdown until an entire core could be off loaded into the SFP and in tabular form, establish and present the heat rate of each batch of discharged fuel taking the number of assemblies discharged and the total decay time of each batch into account.)

and SRP 9.2.5, Branch Technical Position ASB 9-2.

(The use of the. ANS 5. 1-1979, "Decay Heat Power in Light Water Reactor,"

has been found acceptable for the decay heat calculation.

However, the input parameters for using ANS 5.1-1979 will have to be justified.)

2.

Under the conditions outlined above, discuss the minimum pool water volume, heat-up rate, boil-off rate and the time taken for the pool water to reach 212 F.

The analysis should reflect the current fuel design (e.g.

9 x 9 fuel, bundles vs.

8 x 8 fuel bundles),

fuel cycle length (e.g.

18 months vs;- 12 months),

and refueling procedures.

3.

Provide the..results of the calculations of peak temperature or temperature transient and radiation levels in the reactor building and the radiological consequences at the site.

Provide and justify the input parameters used in these computations (e.g. sensible and latent heat loads due to SFP boil-off).

4.

Under the conditions outlined above, discuss whether safety-related equipment in the reactor building is environmentally qualified for the postulated temperatures and radiation levels.

~

~

5. If the SFP is allowed to boil and an engineered safety grade system (e.g.

RHR) is utilized to provide the make-up for the boiling, provide the following information:

a)

The operator actions that would be required to align the systems and the estimated time to accomplish this.

Discuss whether there are procedures to cover these operations and what training has been provided.

b)

As indicated in the FSAR Section 18.1.20.3.4'.3, the results from the current analyses show that the reactor building will be generally inaccessible for several days after a

LOCA due to contained radiation sources.

Provide the basis for whether or not this poses a problem in coping with the loss of SPF cooling. If as a result of your evaluations, you deem that system modifications are warranted, describe what modifications (if any) are being considered.

c)

Identify the equipment and instrumentation (including their locations and qualifications) required to cope with the loss of SFP cooling.

d)

Describe the accessibility and operability (including the effects associated with the resultant environmental conditions, e.g.

temperature, radiation levels, flooding, etc.) of the equipment and instrumentation including the habitability in these areas.

e)

State the total volume of water expected to boil off from the SFP during the course of a LOCA.

f)

Discuss how the condensate from the boil-off will be collected (drained) and treated.