Text

Affidavit of Kw Holtzclaw Supporting Motion for Summary Disposition of Contention B Re Potential Evacuation Route Impediments.Certificate of Svc Encl
	ML20102A858
Person / Time
Site:	Perry
Issue date:	02/04/1985
From:	Holtzclaw K; CLEVELAND ELECTRIC ILLUMINATING CO., GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20102A776	List: ML20102A774; ML20102A784; ML20102A809; ML20102A818; ML20102A832; ML20102A841; ML20102A858;
References
	NUDOCS 8502080596
	Download: ML20102A858 (11)
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-2 UNITED STATES OF AMERICA =8 NUCLEAR REGULATORY COMMISSION -

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BEFORE THE ATOMIC SAFETY AND LICENSING BOARD $

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[ THE CLEVELAND ELECTRIC ) Docket Nos. 50-440 3

ILLUMINATING COMPANY ) 50-441 4

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[ (Perry Nuclear Power Plant, ) .5 Units 1 and 2) ) ;

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! AFFIDAVIT OF '

KEVIN W. HOLTZCLAW l

( ON CONTENTION B 1d L

County of Santa Clara ) i

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! State of California ) {

[ Kevin W. Holtzclaw, being duly sworn, deposes and says: j

, 1. I am Principal Licensing Engineer and Program Manager :

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( of the GE Severe Accident Program, General Electric Company. ]

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! My business address is 175 Curtner Avenue, San Jose, California i l

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95125. Since March 1982, I have managed the BWR/6 standard d Y

plant Probabilistic Risk Assessment and Severe Accident S

E g submittals relating to accident evaluations beyond current g '

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, design bases. A current statement of my professional and 1 I =

technical qualifications is attached hereto. I have personal y

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( knowledge of the matters stated herein and believe them to be d true and correct. I make this affidavit in support of a _

Applicants' Motion for Summary Disposition of Contention B. g

[ 2. Contention B asserts in part that low or no power

m operation at Perry during extreme conditions of inclement g

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weather has not been included in emergency plans. Because of ?

1 the extraordinarily remote probability of an accident occurring $

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A s A I ie 8502080596 850205 j

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PDR ADOCK 05000440 l

i G PDR

Y at the Perry Nuclear Power Plant during extreme conditions of inclement weather, I do not believe that inclusion in emergency plans of a requirement for low or no power operation in such weather conditions is warranted. Neither the likelihood of a severe reactor accident nor-the consequences of such an accident would be significantly reduced if the plant were required to go to low power or no power operation during periods of extreme conditions of inclement weather.

3. There is no significant risk reduction to the public afforded by either " low power" or "no power" operation during periods of inclement weather, for the reasons enumerated in the following paragraphs. For purposes of this affidavit, " low power" operation means power operation in the 15-20% thermal power range, which is the lowest thermal power level which allows electrical generation at Perry. "No power" operation means no electrical power generation at the cold shutdown condition. From the 100% operating power level it would typically require 1-2 hours to decrease the operating level to the low power range and about 3-4 additional hours to achieve cold shutdown status.

4. The likelihood of an accident sequence with the potential for core damage and fission product release is essentially the same, independent of full, low or no power level within the first day following extended full power operation. This is because the ability of water delivery systems to supply adequate core cooling is not affected by low

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r or no power operation. This conclusion is supported by 4

, numerous BWR evaluations (References 1-5) which illustrate the ability of the full complement of systems available to prevent core heatup and potential damage. Thus, at "no. power"

! operation, the Control Rod Drive System (with 2 pumps to deliver water to the core), the Low Pressure Coolant Injection Syst'em (3 pumps for water delivery), the Low Pressure Core Spray System (1 pump), the Condensate Booster Pumps (3 pumps),

the High Pressure Core Spray System (1 pump) would be available. In addition, at full or low power operation, an additional system is available, the Reactor Core Isolation Cooling System (1 pump). Also, in series with the Condensate Booster Pumps, the Feedwater System (2 pumps) becomes operational. Both of these additional sets of pumps are available since they are driven by steam from the reactor.

Furthermore, the accident sequences with the potential for core damage require multiple equipment and/or operational failures which are not related to reactor core status (full, low or no 4

power level).

5. There are a number of contributors to the progression of severe accident sequences. These includes (a) random failures of standby equipment upon demand, such as valves and pumps; (b) equipment unavailability due to normal maintenance and testing activicies during operation; and (c) equipment misalignment or miscalibration, for example, normally open valves left. closed, miscalibrated sensors or instruments.

These examples, which have no dependence on reactor power

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level, illustrate why the likelihood of accident progression is not reduced by a decrease in reactor power.

6. The. consequences of an end of the spectrum, highly improbable event involving a significant offsite release of radiation are negligibly different if the plant is at [bil, low or no power operation during the postulated period'of inclement weather. This is due to the rate of decay of. fission products which remain radiologically active for a long period of time t i

I after shutdown. The fission product inventories are established by full power operation. At low power, tr e is essentially no change in fission product inventory over time compared to full power operation because the reactor remains critical. The inventories'of.the important isotopes do not change appreciably (less than a factor of 2) within a' period from 2-8 hours even after going to a "no power" condition (Reference 6). This slow rate of. decay of the radiologically significant fission products (e.g., cesium, iodine, tellurium, strontium) is attributed to their relatively long half-lives, which range from 8 days (for iodine-131) to 28 years (for l

' strontium-90). .There-are many other isotopes which also remain j radioactive for a long period of time after shutdown. The

[ attached graph representing the change in total core inventory for gamma emitting isotopes ever time demonstrates the relative

( insensitivity of the fission product inventory to time after f

l : shutdown.

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FROM ? 41 '35.02.04 :" 20 4

7. In summary, low or no power operation would not significantly change either the likelihood of an accident scenario leading to off-site doses or the resultant. off-stte doses themselves and would therefore not.-

significantly reduce the radiological risk to-the health and safety of the-public.

STATE OF CALIFORNIA ) SS COUNTY OF SANTA CLARA )

Kevin W. Holtzclaw, being duly sworn. deposer ead says: .

1 hat-he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledga, infsr;;;stion, and - -

belief.

Executed at San Jose, California, this Wh day of-AirJvwary- , 198 5 .

Man W Kevin W. Holtzcla #

Subscribed and sworn before me this day of [fgE// At/L,196[ -

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OFr!CML SEAL j f y,{h &

N@T/94, PUBLIC, STATE Of/ CALIFORNIA i

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%- VAGE'4 5 VOGELHUBER v

cTA::7 r;; .:0 CAL'?cnkw - . - - - - - -

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, surn cawcar-- -

Hy come, espires DEc 30, 1988 l

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REFERENCES i

1. Reactor Safety Study (RSS): An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, WASH-1400 (NUREG-75/014, USNRC, October 1975.

2. Probabilistic Risk Assessment Limerick Generating Station, Philadelphia Electric Company, Docket Nos. 50-352, 50-353, March 1981.

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3. _ Final Report: Probabilistic Risk Assessment Shoreham Nuclear Power Station, Long Island Lighting Company, prepared by Science Applications, Inc. SAI-372-83-PA-01, June 24, 1983.

4. Reactor Safety Study Methodology Applications Program: Grand Gulf No. 1 BWR Power Plant, Prepared by Sandia National Laboratory and Battelle Columbus Laboratory, NUREG/CR-1659 (SAND-80-1897), October 1981.

5. GESSAR II 238 Nuclear Island, GE Document No. 22A7007, Rev. 2, Appendix 15D: Severe Accidents, Docket No. 50-447, May 1982.

6. Calculation of Fission Product Inventory and SPECTRA-RADCIOl Program, General Electric Report NEDO-25176, October 1980.

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KEVIN W. HOLTZCLAW EDUCATION B.S. Mechanical Engineering (Nuclear Option), 1 San Jose State University, 1968 1 M.S. Mechanical Engineering, University of California, 1973 General Electric Advanced Courses in Engineering, 1969-71 POSITIONS HELD March 1982 - Present Principal Licensing Engineer, Program Manager of the GE Severe Accident Program February 1980 - Senior Licensing Engineer BWR Systems March 1982 Licensing (GE)

June 1974 - Technical Leader, Fuel Applications and February 1980 Thermal Design (GE)

January 1971 - Engineer, Fuel Applications and Thermal' June 1974 Design (GE)

July 1969 - Program Engineer, Fuel Performance and January 1971 Applications (GE)

June 1968 - Engineer - Nuclear Power Department (San July 1969 Francisco Bay Naval Shipyard)

EXPERIENCE As a senior licensing engineer from 1980 through 1982, Mr.

Holtzclaw was responsible for defining and planning programs related to NRC degraded core rulemaking.- He also provided the safety and licensing program management for the Limerick Probabilistic Risk Analysis. He also acted as the GE representative on AIF Industry Degraded Core Rulemaking Technical Advisory Group.

Since March 1982, Mr. Holtzclaw has served as the GE Program Manager of the GE Severe Accident Program. This has entailed managing the BWR/6 standard plant Probabilistic Risk Assessment and Severe Accident submittals relating to evaluations'beyond current design basis. He continued to act as the GE

-representative on the Industry Degraded Core Rulemaking (IDCOR)

Technical Advisory Group. He has been the responsible engineer in the GE Safety and Licensing organization-for the GE. Fission Product Retention Program and Severe Accident Source Terms and for programs ~ relating to hydrogen generation and control.

Mr. Holtzclaw was an engineer and technical leader in General Electric's Fuel Design Department from 1969 to 1980 responsible

s for performing Reload and Initial Core Fuel Thermal and Thermal-Hydraulic fuel design and safety analyses. He had principal responsibilities in development of thermal analysis methods, the design and licensing of 8x8 fuel and extended exposure fuel designs, and in defining acceptance criteria for fuel thermal-mechanical fuel integrity properties and capabilities.

l He also worked one year as a mechanical design engineer in the '

nuclear power department of the San Francisco Bay. Naval Shipyard.

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UNITED STATES OF AMERICA

+

NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD

.a

. : b $ 0 I. L In the Matter of )

)

THE' CLEVELAND ELECTRIC ) Docket Nos. 50-440 '

ILLUMINATING COMPANY ) 441

)

(Perry Nuclear Power Plant, )

Units 1 and 2) )

, CERTIFICATE OF SERVICE I hereby certify that copies of " Applicants' Motion For

- Summary Disposition of Contention B," " Applicants' Statement of ,

Material Facts As-To Which There Is No Genuine Issue To Be Heard on Contention B," " Affidavit of Daniel D . Hulbert on Contention B," " Affidavit of Gary Winters on Contention B , "

" Affidavit of Scott T. McCandless on Contention B," " Affidavit

of Richard R. Bowers on Contention B," and " Affidavit of Kevin i

-Holtzclaw on Contention B" were served this .Sth day of February, 1985, by deposit in the U.S. mail, first clssa, post-L age prepaid, upon the parties listed on the attached Service l

l~ List, except for those parties identified by asterisk who were l

served by hand delivery.

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V

. Jay' . 31 berg -

Dated: February 5, 1985 i

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4 UNITED-STATES OF AMERICA NUCLEAR REGULATORY COMMISSION r ,

i BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

.THE CLEVELAND ELECTRIC ) Docket Nos. 50-440 ILLUMINATING COMPANY, ET AL. ) 50-441 l.-

)

(Perry Nuclear Power Plant, )

Units 1 and 2) )

4 SERVICE LIST James P. Gleason, Chairman Atomic Safety and Licensing 513 Gilmoure Drive Appeal Board Panel Silver Spring, Maryland 20901 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Jerry R. Kline Docketing and Service Section l Atomic Safety and Licensing Board Office of the Secretary U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Mr. Glenn O. Bright a Colleen P._ Woodhead, Esquire Atomic Safety and' Licensing Board Office of the Executive Legal U.S. Nuclear. Regulatory Commission Director .

Washington, D.C. 20555 U.S. Nuclear Regulatory Commission

' Washington, D.C. 20555 Alan S. Rosenthal, Chairman Atomic Safety and Licensing $ Terry Lodge, Esquire Appeal' Board Suite 105 U.S. Nuclear Regulatory Commission 618 N. Michigan Street Washington, D.C. 20555 Toledo, Ohio 43624 L Dr. W. Reed Johnson Donald T. Ezzone, Esquire j Atomic Safety and Licensing Assistant Prosecuting Attorney l Appeal Board Lake County Administration l U.S. Nuclear Regulatory Commission Center L washington, D.C. 20555 105 Center Street l Painesville, Ohio 44077 l Gary J. Edles, Esquire

!. Atomic Safety and Licensing- Atomic Safety and. Licensing L

Appeal Board Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission

. Washington, D.C. 20555 Washington, D.C. 20555

i. -

l John G. Cardinal, Esquire -utMs. Sue Hiatt l' Prosecuting Attorney 8275 Munson Avenue l Ashtabula County Courthouse Mentor, Ohio 44060 Jefferson, Ohio 44047'

- - . _ . - - - - . _-._ _..-._ _ ____ _ _ ._ _ ._ ,_._ _ _ _.-. _ _i,___ ._ _ -.__._.__. _ . _ .

ML20102A858

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