ML20211N901

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Forwards Request for Addl Info Related to License Amend Submittal Dtd 970909,addressing Analysis Rev for Makeup Sys Letdown Line Failure Accident
ML20211N901
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/10/1997
From: Raghavan L
NRC (Affiliation Not Assigned)
To: Richard Anderson
FLORIDA POWER CORP.
References
TAC-M99571, NUDOCS 9710170162
Download: ML20211N901 (5)


Text

October 10,z 1997

--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:

. CRYSTAL RIVER UNIT 3 --REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO REVISED ANALYSIS OF MAKEUP SYSTEM LETDOWN LINE FAILURE ACCIDENT (TAC NO. M99571)

Dear Mr. Anderson:

The purpose of this letter is to' request addit'ional information (RAI) relating

. to your license amendment- submittal dated September 9.1997, addressing analysis revision' for..the makeup system letdown hne -failure accident. The enclosure provides details for the requested-information.

We request your response as:soon as possible so that we can schedule our t review effort consistent'with1your restart plan. If you have any questions, please write or call me at (301) 415-1471; Sincerely, t L.Maghavan.ProjectManager

-Project Directorate II-3 Division of-Reactor Projects - 1/II

' Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

PAI cc: -See next page

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J. Jaudon. Region-II DOCUMENT NAME: G:\ CRYSTAL \99571.rai To receive = a copy of this document, indicate in the box: "C" - Copy without

, 1 attachment / enclosure "E" = Copy with attachment / enclosure- "N" - No copy OFFICE P0ll-3/PM , l [P011 3/LA l l PDII 3/D A gl l ) i i NAME LRaghaven W 8Clayton /f AV FMebdon M OATE 10/ 9 /97 10/ 9 /97 10/ /97 10/ #J/97' 10/ /97 10/ /97 9710170162 971010 PDR ADCCK 05000302 P PDR . ? *s P ll-l ll ll. . . ,

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% ,,,,, # October 10, 1997 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 SUBJEU: CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION - LICENSE AMENDMENT RELATED TO REVISED ANALYSIS OF MAKEUP SYSTEM LETDOWN LINE l FAILURE ACCIDENT (TAC NO. M99571) l

Dear Mr. Anderson:

I The purpose of this letter is to request additional information (RAI) relating to your license amendment submittal dated September 9.1997, addressing analysis revision for the makeup system letdown line failure accident. The enclosure provides details for the requested information.

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

L. Raghavan. Project Manager Project Directorate II-3 Division of Reactor Projects - I/II

.0ffice of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc: See next page

l 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 13760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Charles Pardee, Director Nuclear Plant Operations (NA20) Senior Resident Inspector Florida Power Corporation Crystal River Unit 3 Crystal River Energy Complex U.S. Nuclear Regulatory Comission 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 (SA2C)

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 II 1317 Winewood Blvd. U.S. Nuclear Regulatory Comission Tallahassee, Florida 32399-0700 61 Forsyth Street, SW., Suite 23T85 Atlanta, Gh 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 Comissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-424b l

l

RE00EST FOR ADDITIONAL INFORhATION LICENSE AMENDMENT MAKEUP SYSTEM LETDOWN LINE FAILURE ACCIDENT (TAC NO. M99571)

1. Based on our review of various Crystal River Unit 3 documents our urjderstanding ,

of the control complex habitability envelope (CCHE) configuration and operation  !

is tabulated below. Please confirm these data:

Normal ooerations orior to event:

~

AHF-19A(B) 42.335 cfm AHF-17A(B)- 48.000 cfm l AHF-21A(B) 4.805 cfm l AHF-20A(B) 10.655 cfm  !

AHF 5.390 cfm l

D-12 adjusted for 5.260 cfm D-1/D-1D adjusted for 5,700 cfm D shut D-3 open (passing 42,335 cfm)

After recirculation mode actuation AHF-19A(B) 42.335 cfm AHF-17A(6) 48.000 cfm (stopped manually after 30 minute delay)

AHF-18A(B) 43,500 cfm (started manually after 30 minute delay)

AHF-21A(B) stopped AHF-20A(B) stopped AHF-30 stopped D-12 shut l

D-1/D-1D shut D-2 shut D open-(passing 42.335 cfm)

2. For the letdown line event, at what time would control room automatic isolation and shift to recirculation occur? If automatic isolation does not occur (same

-signal that would have isolated letdown?), what is a conservative estimate of time for operator to actuate this shift to recirculation? (i.e., what is curation of unfiltered 5700 cfm intake after start of letdown line release but prior to isolation?)

3. If automatic isolation and shift to recirculation is based on recirculation line radiation monitor alarm, provide basis of alarm response, e.g., equivalent isotopic concentration in duct (particularly that for iodine). Include any expected delays, e.g., damper movement: diesel sequencing of dampers, monitors.
4. Confirm that the mass release estimate of 114.000 lbm from the letdown line is based on the total time to leakage isolaticn at 1170 seconds.
5. Provide justification for not assuming that the system depressurization associated spike.

with the letdown line failure results in an incident-induced iodine Enclosure

-6 Submittal does not address the impact of the )roposed change on the control room habitability. Please discuss the impact of tie letdown line failure on the control complex habitability to satisfy your final safety analysis report (FSAR)

-Criterion 11 (General Design Criterion 19). Please address impact of differences in source mix, source magnitude (including iodine spike) and accident progression on automatic and manual control. room isolation actions.

7 .: Short-term accident dispersion values are tabulated in FSAR Tables 2-18, 14-23.

and 14-52. -The values in Table 14-23 differ in magnitude (lower) from those in the other tables. Which values are currently applicable to design basis calculations at Crystal River?

' 8. We understand that volume ~of the CCHE is 355.311 cubic feet, of which. 85,573 cubic feet is the actual control room. Please:

(a) provide the volume of the area supplied by damper 0-12. and AHF-30 and exhausted by AHF-20A/B and the volume of the equipment room exhausted by AHF-21A/B.

(b)- confirm whether they are free volumes s'c) confirm whether the CCHE and control room volumes specified above include I

volumes discussed in (a) above.

l ,

a Enclosure

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