ML20199J359

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Forwards Request for Addl Info Re Crystal River 3 Nuclear Plant,Summary Rept on Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,
ML20199J359
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/02/1998
From: Raghavan L
NRC (Affiliation Not Assigned)
To: Richard Anderson
FLORIDA POWER CORP.
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69440, NUDOCS 9802050292
Download: ML20199J359 (5)


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _

t February 2, 1998 Mr, Rty A. Anderson

. Senior Vice President Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing I

Crystal River Energy Complex (SA2A) 15760 W Power Line Street Cryst.I River, Florida 34428-6708

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE CRYSTAL I

RIVER 3 NUCLEAR PLANT,

SUMMARY

REPORT ON THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED DECEMBER 31,1995 (TAC NO. M69440)

Dear Mr. Anderson:

During the week of November 3,1997, the U.S. Nuclear Reguitaory Commission staff (NRC or the staff) performed an audit of implementation of your plant specific criteria and procedures for verifying the seismic adequacy of equipment at Crystal River Unit 3 (CR-3) for the resolution of unresolved safety issue (USl A-46)" Seismic Qualification of Equipment in Operating Plants" as delineated in Generic Letter (GL) 87-02. Our review of your submittals relating to the USl is in progress. The staff has determined that it needs certain additional information to complete its review, The enclosure provides the details of the information requested.

We request your response within 45 days. If this is not achievable, FPC should notify the NRC staff and propose a date for submiLal of a response to the request for additional information (RAI). Should you have any questions related to this letter or the enclosed RAI, please contact me at (301) 415-1471.

Sincerely,

/S/

L. Raghavan, Project Manager Project Directorate 11 Division of Reactor Projects - 1/ll Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc w/ enclosure: See next page y@{ g g

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February 2, 1998 1

Mr. Roy A. Anderson Senior Vice President Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE CRYSTAL RIVER 3 NUCLEAR PLANT,

SUMMARY

REPORT ON THE VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, DATED DECEMBER 31,1995 (TAC NO. M69440)

Dear Mr. Anderson:

During the week of November 3,1997, the U.S. Nuclear Reguitaory Commission staff (NRC or the staff) performed an audit of implementation of your plant-specific criteria and procedures for verifying the seismic adequacy of equipment at Crystal River Unit 3 (CR-3) for the resolution of unresolved safety issue (USl A-46) " Seismic Qualification of Equipment in Operating Plants" as delineated in Generic Letter (GL) 87-02. Our review of your submittals relating to the USI is in progress. The staff has determined that it needs certain additionalinformation to complete its review. The enclosure provides the details of the information requested.

We request your response within 45 days. If this is not achievable, FPC should notW the NRC l

staff and propose a date for submittal of a response to the request for additionalinformation (RAI). Should you have any questions related to this letter or the enclosed RAl, please contact me at (301) 415-1471.

Sincerely, N

L. Raghavan, Project Manager Project Directorate ll-3 Division of Reactor Projects - 1/11 Office of Nu;! ear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc w/ enclosure: See next page

s.,

R.

Mr. Roy A. Anderson CRYSTAL RIVER UNIT NO. 3 Flodda Power Corporation cc:

Mr. R. Alexander Glenn Chairman Corporate Counsel Board of County Commissioners Florida Power Corporation Citrus County MAC A5A -

110 North Apopka Avenue P.O. Box 14042 -

Ivemess, Florida 34450-4245 St. Petersburg, Florida 33733-4042 Mr. Robert E. Grazio, Director Mr. Charles G. Pardee, Director '

Nuclear Regulatory Affairs (SA2A)

Nuclear Plant Operations (NA2C)

Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex

- 15760 W. Power Line Street -

15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428 6708 Senior Resident inspector

- Mr. Bruce J. Hickle, Director Crystal River Unit 3 :

Director, Restart (NA2C)

U.S. Nuclear Regulatory Commission -

Florida Power Corooration 6745 N. Tallahassee Road Crystal River Energy Complex Crystal River, Florida 34428 15760 W. Power Line Street.

= Crystal River, Florida 34428-6708 Mr. John P. Cowa, Vice President, Nuclear Production Mr. Robert B. Borsum (NA2E) -

Framatome Technologies Inc.

Florida Power Corporation-1700 Rockville Pike, Suite 525 Crystal River Energy Complex -

Rockville, Maryland 20852 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Bill Passetti Office of Radiation Control

- Mr. James S. Baumstark Department of Health and Director. Quality Programs (SA2C)

Rehabilitative Services Florida Power Corporation 1317 Winewood Blvd.'

Crystal River Energy Complex

. Tallahassee, Florida 32399-0700 -

15760 W. Power Line Street Crystal River, Florida 34428-6708 Attomey General.

Department of Legal Affairs-Regional Administrator, Region 11 The Capitol -

U.S. Nuclear Regulatory Commission -

i

- Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303 3415 Mr. Joe Myers, Director Division of Emergency Preparedness Mr. Kerry Landis Department of Community Affairs U.S. Nuclear Regulatory Commission 2740 Centerview Drive -

61 Forsyth Street, SW., Suite 23T85 Tallahassee, Florida 32399-2100 Atlanta, GA 30303-3415 m

i f '

Raouant For Additional Information Renardina the I lemnaea's Analvain on the Verifirmtian of

- Salamic Admanmev of Machaplemi and Elme+rical Enuinment in Ooaratina R*ars. dated Deesmber 31.1995 Crvatal River 3 Nuchar Power Plant By letter dated December 31,1995, Florida Power Corporation (FPC) submitted a summary report on the verification of seismic adequacy of mechanical and electrical equipment in operating reactors. The staffs review of this report has identified areas where additional infctmation is needed in order to complete its review.

1.

Page 2 of the December 31,1995 submittal states in part that 17 " bad actor relays" were evaluated and 15 of those were determined to only generate alarms which would subsequently clear and therefore contact chatter would not be considered a problem.

The remaining two relays would only perform an alarm function and do not impact the operation of the diesels.

Assuming the alarms associated with these 17 relays are expected to annunciate during l.

the seismic event, would the operators have to respond to those annunciators and review the annuncbtor response procedures associated with them for potential action?

How would those additional actions impact the operators ability to implement the Normal, Abnormal, and Emergency Operating Procedures required to place the reector-in a safe shutdown condition?

2.

Items 4.4.11 and 4.4.12 address lighting requirements and state, in part, that the local

. battery powered light units will remain in place and function se required after the event and that supplemental light will be provided by battery powered and plug-in units connected to a diesel-backed outlet.

Describe the analysis performed to verify that local actions which must be taken by.

operators as a result of the event are in areas which are covered by either local battery operated lights or in close prcximity to the diesel-backed units. For those actions which require either diesel-backed or battery powered lighting, is the equipment permanently staged in the areas required to be accessed by the operators? For those units which must be fed from the diesel-backed units, has the loading associated with these pieces of equipment on the diesel been considered?

3.

Section 4.6, Operations Department Review of Safe Shutdown Equipment List (SSEL),

states that plant operations representatives have verified that all equipment required in the operating and emergency procedures for the selected safe shutdown path are included on the SSEL, and that these procedures are adequate for plant response to the seismic event. Additionally, in Section 4.6.1, Conclusion of Operations Department Review, states that while some operator actions are required, adequate staffing, direction and time are available to accomplish the required actions.

Enclosure

a 7.

Describe what reviews were performed to determine if any local operator actions required to safely shutdown the reacter could be affected by potentiaily adverse environmental conditions (such as loss of lighting, excessive heat or humidity, or in-plant barriers) resulting from the seismic event. Describe how staffing was evaluated and describe the reviews which were conducted to ensure operators had adequate time and resources to respond to such events.

4.

Table 5.4, Outliers, of the evaluation report, identify several control room structures which could impact the operator's ability to respond to the seismic event, including the potential for the main control room ceiling to be an interaction source, several non-bolted cabinets, and several non-restrained pieces of equipment (i.e., computer keyboard and stand). Have each of these potential sources ofinteractions been evaluated and have the final resolutions to each been implemented?