ML20235X986

Summary of 870609 Meeting W/Util & Licensee A/E Re Habitability Considerations of Util Proposed Nonpressurized Control Room Arrangement.Listed Comments Will Be Addressed in Future.List of Attendees & Viewgraphs Encl

ML20235X986
Person / Time
Site:	Crystal River
Issue date:	06/25/1987
From:	Silver H Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8707250014
Download: ML20235X986 (30)

Text

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j#" %4{o, e . UNITED STATES

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[j,.s.d'.i NUCLEAR REGULATORY COMMISSION WASWNGTON, D. C. 20555

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(%.... / June 25, 1987

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1 LICENSEE: Florida Power Corporation (FPC)

FACILITY: Crystal River Unit 3 (CR-3)

SUBJECT:

MEETING ON CONTROL ROOM HABITABILITY, JUNE 9, 1987 Representatives of the licensee and its architect-engineer met with members ,q of the NRC staff to discuss habitability considerations of FPC's proposed non-pressurized control room arrangement. The attendance list is enclosed.

The licensee's presentation was based on the enclosed slides. During the dis-cussion the following comments were made, which FPC stated would be addressed in their upcoming submittal.

All accidents should be evaluated to assure that the bounding acci-dent is used for dose analysis.

In the event of failure of RMA-5, how is it assured that normal ven-tilation fans are tripped and emergency fans / filters are started?

The analyses are based on 0.06 air changes per hour (355 CFM inleakage). How will it be assured that this leakage will not be ex-ceeded, e.g., that doors are not propped open?

_ Discuss administrative contols on past and future sealing of penetra-tions and other openings.

Silicone sealants are difficult to install properly, and may deterio-rate over time. Discuss these points as well as the possible need for some kind of testing to verify leakage assumptions.

What would be involved in a one-time leakage / demonstration test?

Justify the conservatism of the 355 CFii inleakage assumption. What inleakage would result in SRP 6.4 acceptance criteria? What dose would result from actual eApected leakage? Provide sufficient data to per-mit independent NRC analysis. )

j FPC noted inconsistencies in the identification of acceptable 50 c centrationinthecontrolroom(5 PPM,perR.G.1.78)andotherheon-cognized sources, and noted that its analysis results in a 2 minute maximum concentration of 38 PPM. NRC perscnnel emphasized the impor-tance of assuring no significant irritation to the operators which might reduce their performance levels. Another problem noted is the 8707250014 870625 I DR ADDCK 0500 '2 s

I l

L. fairly frequent non-operability of the existing S02 detectors. It I was also noted that reliance on the S02. detector at the Unit 1/2 502

! tank reduces the 2 minute concentration to 4.4 PPM. However, these

l. detectors are not presently caused by the Technical Specifications.

j:

Harley Silver, Senior Project Manager Project Directorate II-2 Division of Reactor Projects-I/II

Enclosures:

As stated cc w/ enclosures:

See next page.

DISTRIBUTION Docket File NRC PDR' Local PDR PD22 Rdg.

H. Silver 0GC-Bethesda E. Jordan J. Partlow ACRS (10) i I

B. Troskeski J. Wing R. Perfetti C. Nichols I. Spickler I

Lf er 2

6f PM:PDII-2 HSilver:bg SPLB P Q

D:PDII-2 DM' CNichols .I$ i er LRubenstein 6/g87 6/73./87 6/29/87 /87 6/9g87' r CW '

Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and Genc al Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor i P. O. Box 14042 The Capitol Buildir.g St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee Mr, F. Alex Griffin, Chaiman Director, Nuclear Plant Operations Board of County Commissioners-Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue ,!

Crystal River, Florida 32629 Inverness, Florida 36250

)

Mr. Robert B. Borsum Mr. E. C. Simpson  !

Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Florida Power Corporation Support Suite 220, 7910 Woodmont Avenue P.O. Box 219 I Bethesda, Maryland 20814 Crystal River, Florida 32629 Resident Inspector l U.S. Nuclear Regulatory Comission 15760 West Powerline Street Crystal River, Florida 32629

. Regional Administrator, Region'II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Jacob Daniel Nash Office of Radiation Control i Department of Health and 1 Rehabilitative Services l 1317 Winewnod Blvd.

l Tallahassee, Florida 32399-0700 Administrator )

Department of Environmental Regulation '

Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 l

ENCLOSURE 1 CONTROL ROOY HABITABILITY MEETING JUNE 9, 1987 Name Affiliation H. Silver NRC NRR PM .

j T. Stetka NRC Senior Resident Inspector R. Vaughn GAI PM P. Bunker GAI - Applied Engineering-M. Cambria GAI - Applied Engineering J. Wing NRC Chemical Engineering Branch-R. Clauson- FPC - I&C Engineer R. Widell FPC - Director, Engineering.& Projects l R. Perfetti NPC - Plant Systems. Branch C. Nichols NRC - Plant Systems Branch I. Spickler NRR - Rad. Protection Branch D. Shook FPC - Manager Nuclear Elect /I&C Eng.

C. Kramer G/C, Inc. - Controls Systems Project Eng.

E. Good FPC Sr. Nuclear Licensing Engineer D. Ramos G/C, Inc. HVAC l

CRYSTAL RIVER UNIT 3 CONTROL ROOM HABITABILITY AGENDA e INTRODUCTION e HVAC SYSTEM DESCRIPTION ,

NORMAL OPERATION EMERGENCY OPERATION e DESCRIPTION OF THE CONTROL COMPLEX HABITABILITY ENVELOPE e PRESSURIZED vs. UNPRESSURIZED CONTROL- ROOM TYPES OF CONTROL ROOM HVAC SYSTEMS l e CONTROL COMPLEX LEAKAGE REDUCTION MODIFICATIONS BUILDING LEAKAGE l

PENETRATION AIR SEALS (PASSIVE)

DOOR AIR SEALS ( ACTIVE) l HVAC SYSTEM'S CONTROL-FANS AND DAMPER CONTROL DAMPER POSITION INDICATION l

1 e RADIOLOGICAL EVALUATION  !

CRITERIA MODEL RESULTS e HAZARDOUS CHEMICAL EVALUATION CRITERIA / REGULATIONS METHODOLOGY RESULTS j

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1 CRYSTAL RIVER UNIT 3 CONTROL ROOM HABITABILITY REASONS FOR SELECTING RECIRCULATION (TYPEII) SYSTEM 1

Recirculation system has a much higher potential for 1.

controlling iodine than those having once-through filters.

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2. Recirculation system does not depend on outside make-up air' for protection, thus unfilterable activity (nobel gases) which contributes to the whole body gamma exposure, is not being drawn into the control room envelope. i Recirculation system provides protection for both lodine

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4. Simplifies system operation.

5. Recirculation system with in-leakage rate equal to 'or greater than 0.06 air volume change per hour requires less surveillance testing.

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6. The existing system is more compatible to recirculation than pressurization.

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Zone isolation With Filtered Recirculated l Mode Of Operation Air {

Habitability Envelope Free Volume (ft3) 355,311 )

Infiltration Rate Through Closed Air $gg Intake isolation Damper (SCFM) i t

infiltration Rate For Opening And 10 Closing Doors (SCFM)

Habitability Envelope Infiltration Rate 0.06 Air Volume Changes Per Hour (SCFM)

Filtered Recirculation Flow Rate (SCFM) 43,500 l l

Recirculation Charcoal Filter Bed Depth 2

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Filter Efficiency For lodines 95% For All Species  !

Control Room X/Q Values (sec/m3) 0- 8 Hrs. 9.00 x 10 4 0 - 24 H rs. 5.31 x 10-4 1- 4 Days 2.07 x 10 4 l 4 30 Days 5.94 x 10-5 Breathing Rate For Operators in 3.47 x 10-4 Control Room (m3/sec)

Recirculation Loop Leakage (cc/ min) 4510 SRP Assumed Leakage 50 gpm For 30 Minutes Starting 24 Hours After Accident Sump Liquid Volume Post-LOCA (gal) 490,182 Fraction Of Recirculation Loop Leakage 10 Flashing To Steam (percent)

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CRYSTAL RIVER UNIT 3 COrdIROL ROOM HABITABILITY ASSESSMENT PROTECTION ACTION LIMIT (2 MIN.)

SULFUR DIOXIDE o - REGULATORY GUIDE 1;78 PROVIDES INCONSISTENT LIMIT VALUES ( 5 PPM / 26 MG / M3 )

o OSHA LIMIT FOR 8-HOUR DAILY EXPOSURE IS.5 PPM s SAX SPECIFIES THAT 50-100 PPM 15 MPC FOR EXPOSURES OF 30 60 MINUTES e MATHESON SPECIFIES TH AT' 150 PPM CAN ONLY BE TOLERATED FOR FEW MINUTES I

e NUREG /CR-1741 PROVIDES MODEL TO ESTIMATE INCAPACITATION TIME e BASED ON MODELS AND LITERATURE, A~ LIMIT OF 125 PPM '

. WAS SELECTED .

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