ML20217G852

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Forwards RAI Re 970729 Amend Request for Change to PAM Instrumentation TS
ML20217G852
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/07/1997
From: Raghavan L
NRC (Affiliation Not Assigned)
To: Richard Anderson
FLORIDA POWER CORP.
References
TAC-M99308, NUDOCS 9710140252
Download: ML20217G852 (4)


Text

.- October 7, .1997 Mr. Roy A. Anderson ,

Senior Vice President Nuclear Operations  !

Florida Power Corporation i ATTN: Manager. Nuclear Licensing i Crystal River Energy Complex (SA2A)  !

15760 W Power Line Street 1 Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 209.

REVISION 1. POST-ACCIDENT MONITORING INSTRUMENTATION (TAC NO. M99308)

Dear Mr. Anderson:

The pucoose of this letter is to request additional information (RAI) relating to your license amendment submittal dated July 29, 1997. requesting a change to the Post-Accident Monitoring (PAM) instrumentation technical specification.

The enclosure provides the detail for the requested information.

We request your response as soon as possible so that we can schedule our.

review effort consistent with your restart plan. If you have any questions, olease write or call me at (301) 415-1471.

Sincerely.

. -- b.M L. Raghavar-[. Project Manager-Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI g cc: See next page g'

Distribution ~

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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 l

SUBJECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 209, i

REVISION 1. POST-ACCIDENT MONITORING INSTRUMENTATION l (TAC NO. M99308)

Dear Mr. Anderson:

The purpose of this letter is to request additional information (RAI) relating to your license amendment submittal dated July 29, 1997, requesting a change to the Post-Accident Monitoring (PAM) instrumentation technical specification.

The enclosure provides the detail for the requested information.

We request your response as soon as possible so that we can schedule our review effort consistent with your restart plan. If you have any questions, please write or call me at (301) 415-1471.

Sincerely, Y >

L. Raghavan. Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc: See next page s

9 Mr. Roy A. Anderson CRYSTAL RIVER UNIT N0. 3 Florida Power Corporation cc:

Mr. R. Alexander Glenn .

Corporate Counsel Mr. Robert E. Grazio, Director Florida Power Corporation Nuclear Regulatory Affairs (SA2A)

MAC-A5A Florida Power Corporation P.O. Box 14042 Crystal River Energy Complex St. Petersburg, Florida 33733-4042 15760 W. Power Line Street l

Crystal River, Florida 34428-6708 Mr. Charles Pardee, Director Nuclear Plant Operations (NA2C) Senior Resident Inspector Florida Power Corporation Crystal Ri/er Unit 3 Crystal River Energy Complex U.S. Nuclear Regulatory Commission 15760 W. Power Line Street 6745 N. Tallahassee Road Crystal River, Florida 34428-6708 Crystal River, Florida 34428 Mr. Bruce J. Hickle, Director Mr. John P. Cowan Director, Restart (NA20) Vice President, Nuclear Production Florida Power Corporation (NA2E)

Crystal River Energy Complex Florida Power Corporation 15760 W. Power Line Street Crystal River Energy Complex Crystal River, Florida 34428-6708 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Robert B. Borsum B&W Nuclear Technologies Mr. James S. Baumstark 1700 Rockville Pike, Suite 525 Director, Quality Programs (SA20)

Rockville, Maryland 20852 Florida Power Corporation Crystal River Energy Complex Mr. Bill Passetti 15760 W. Power Line Street Office of Radiation Control Crystal River, Florida 34428-6708 Department of Health and Rehabilitative Services Regional Administrator, Region 11 1317 Winewood Blvd. U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Attorney General Department of Legal Affairs Mr. Kerry Landis The Capitol U.S. Nuclear Regulatory Commission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245

REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO TECHNICAL ,

SPECIFICATION CHANGE REQUEST NO. 209. REVISION 1. POST-ACCIDENT MONITORING INSTRUMENTATION (TAC NO. M99308)

1. In Attachment F (page 1. second paragra)h) of the July 29, 1997,

-submittal. Florida Power Corporation (F)C) states that "all inputs used by the Safety Parameter Display System (SPDS) to calculate subcooling margin are environmentally qualified." However. Attachment ') (marked up Technical Specifications page B 3.3-138a. item 21) states toat "the core exit thermocouple inputs to the subcooling margin monitors are not environmentally qualified." The statements appear contradictory, please clarify.

2. In Attachment I (Jage 2) of the July 29. 1997, submittal. FPC states that a backup metlod for calculating T-SAT is a manual calculation b operators using input from core exit thermocouples and steam tables.y With regard to the manual calculation, the staff would like the following:
a. A description of the conditions or actions that initiates the operator to begin the manual . calculation,
b. A description of the information needed by the operator to complete the manual calculation. In your response, please discuss how readily available this information is to the operator,
c. An estimate of the time necessary for the. operator to complete the manual calculation. Please provide the basis for your answer.

{

d. A descriation of the training provided to the operators-to assure t1at they are able to complete the calculation accurately and in the time-period allotted.

3;

-- Attachment F provides FPC's evaluation of the SPDS against the design criteria of Regulatory Guide (RG) 1.97 " Instrumentation for Light-Water-

. Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." The design criteria in RG 1.97 states that " redundant or diverse channels should be electrically independent and physically separated from each other and from equipment not classified important to safety in accordance with RG 1.75 ' Physical Independence of Electrical Systems'." Please discuss how physical separation for the SPDS cabling will be achieved.

Enclosure