ML20040A249

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Summary of 780728 Meeting W/B&W Re Resolution of Issue of Achievement of Cold Shutdown Using safety-grade Equipment. Attendance List,Presentation Matl & Draft Summary Encl
ML20040A249
Person / Time
Site: 05000561
Issue date: 09/07/1978
From: Cox T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201200616
Download: ML20040A249 (35)
v • d • e


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l UNITED STATES

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SEP 7 1978

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i' Docket No. STN 50-561 VENDOR:

Babcock & Wilcox Company (B&W)

SUBJECT:

SulHARY OF JULY 28,1978 MEETING ON RESOLUTION OF ISSUE CONCERNING ACHIEVEMENT OF COLD SHUTOOWN USING SAFETY GRADE EQUIPMENT

Background

The BSAR-205 preliminary Design Approval and Safety Evaluation Report (NUREG-0433) were issued on May 31, 1978. These documents require that the cold shutdown issue be addressed by B&W in the post-preliminary design appro-val period, and that applications referencing the BSAR-205 design provide l

design criteria and designs that are consistent with the requirements for the The BSAR-205 Safety Evaluation Report identified seven re-BSAR-205 design.

quirements applicable to the BSAR-205 design and the designs of the balance-of-l plant portions of applications _ referencing BSAR-205.

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At a meeting on June 16, 1978 B&W and the staff discussed the staff requirements and BE's views on those requirements. On June 28, 1978, B&W

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met with their clients to discuss the staff requirements and potential solu-tions thereto. Subsequent to their June 28 meeting with the B&W owner's group, B&W met again with the staff on July 28, 1978, to present BW's current status of plans to comply with staff requirements and to receive staff coments on information transmitted by B&W at both the June 16 and July 28 meetings.

An attendance list and copies of the presentation material are attached.

Sumary J. Taylor of B&W opened the discussion by reiterating their position that the risk reduction inherent in going to cold shutdown in approximately 1-1/2 days, using only safety grade equipment, rather than proceeding to and main-taining hot shutdown indefinitely, is not significant and is unjustified.

l D. Newton and E. Swanson presented the proposed B&W approach to meeting i

the staff requirements expressed on page 5-21 of the staff Safety Evaluation Report. (SER). Each of the staff requirements were discussed except item (6')

in the SER, which requires certain procedures to be provided concerning cool-down using natural circulation.

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r Meeting Sumary SEP 7 1978 The main points of the discussion for each item are included in following paragraphs.

Safety-grade steam generator dump valve - D. Newton described 1.

B&W's valve, termed the modulating atmospheric dump valve (MADV).

The valves, one for each steam generator, will be located on the ma n steam line between the containment wall and the main steam i

isolation valve. Valves will be seismic Category 1, air operated, with Class lE electrical control power. B&W also stated that, for BSAR-205, the valves will be purchased to comply witn the operability assurance requirements of Regulatory Guide 1.48, to j

assure that the valve performance capability will be maintained after a safe shutdown earthquake (SSE). Current BSAR-205 inter-face requirements provide for up to one-half hour of safety-grade air as the motive power supply. B&W proposes that after the air suppl is expended, the valves could be manually adjusted (hand-wheel at the valve location.

T. Novak stated that the staff position on the current BSAR-205 design is that the number of MADV's is inadequate. B&W's calcu-lations indicate that if one of the two available valves was mechanically stuck closed, the plant cooldown time would be

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extended to at least several days. The staff considers this time excessive. The staff further questioned the effect of such

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reduced cooling capacity on the capability for natural circulation in the reactor coolant loops.

T. Novak stated that the staff will require that all B&W plants incorporate at least two MADV's per steam generator, to assure adequate system cooling in the event of the inability to open one valve.

V. Benaroya stated that the current staff position is that, for applications not yet docketed, local manual operation of the MADV's will not be acceptable, except to mitigate the l

consequences of a single active failure. Operation from the i

control room, for the time necessary to cool the plant to initiation i

of the decay heat removal system, will be required. Local manual i

operation, if necessary, would be apprbved for dump valves in plants now under construction and for active applications for which an SER has been written. For plants using a B&W steam system, these would include Greene County, pebble Springs, WNP-1, 4, Bellefonte and Erie 1, 2.

Justification for the acceptability of local operation must include actual local test operation of the MADV's, showing that the plant can be cooled in a controlled manner and that the MADV's can be operated safely and effectively.

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Meeting Sumary SEP 7 1975 F

2.

Cooldown. capability - This discussion is reported under item 1

above, j

3.

Seismic Category 1 auxiliary feedwater supply - The current i

BSAR-205 requirements indicate that a supply for at least four hours operation at hot shutdown is required. Little discussion l

i was held on this requirement since the water supply is the t

responsibility of a referencing applicant. B&W indicated that they consider that appropria.te interface requirements have been specified in BSAR-205.

4.

Depressurization - B&W representatives described three methods l

of depressurizing the reactor coolant system:

using the pressurizer auxiliary spray system using the pressurizer Electromatic relief valve using the ECCS high pressure injection system to inject relatively cool water into the reactor coolant system.

j Only (c) above will incorporate fully' safety-grade equipment.

I B&W stated their opinion that because of the number of methods and equipment available, further analysis would show that the l

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BSAR-205 design could be depressurized while meeting the staff single failure requirement and other requirements of the staff position. Staff members present tentatively agreed that the design appeared to include systems and equipment which, in con-i junction with certain manual operations, would probably meet i

staff requirements for the 205 fuel assembly class of plants.

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Boration capability - D. Newton described the B&W equipment that' l

would provide for a cold shutdown reactivity margin of 1% with l

all control rods assumed in the reactor.

T. Novak stated that l

the staff position is that cold shutdown must be accomplished after a postulated safe shutdown earthquake and a single active failure, and must be achieved with one control rod assumed out of the reactor. Manual actions may be justified for the BSAR-205 class of plants, but the availability of non-seismic Category 1 i

equipment may not be assumed.

B&W acknowledged that the current design for baron addition com-ponents is such that not all components would be qualified to operate after the postulated event sequence and associated assumptions specified by the staff requirement. They stated that r

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Meeting Sumary l

there would be three different methods available, with current design equipment, to inject the required boren, and that they expected that some upgrading of the current design would probably enable them to meet the staff requirement, assuming that approp-riate manual actions would be justified. After some discussion of the current design boron addition methods, staff members agreed that B&W could probably meet the requirement with certain manual actions and some design changes to existing systems.

A discussion was held on the manual actions that might be acceptable to achieve the depressurization and boration functions.

T. Novak stated that manual actions outside the control room (inside or outside the containment) could be used, if justified, to mitigate the consequences of a single active failure, by operating a system locally or repairing a failed component. The justification discussion by an applicant must address such areas as system and component location and local radiation levels.

6.

Natural circulation and boren mixing testing - The scope of the required tests was discussed. Participants agreed that even the preliminary design of the actual tests would have to follow com-plation of any system design modifications or planned manual actions that might evolve from vendor and referencing applicant compliance

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with other requirements of the cold shutdown position.

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r T. Novak stated that a single prototype qualification test on t

the lead plant of a given design would be required. However, l

other tests might be required of individual referencing applicants l

if differences in system or component arrangement, or procedural differences, raised new questions concerning accessibility or i

safety for manual actions, or other concerns not addressed by the initial prototype qualification test.

B&W stated that at this time, they could make no comitments f

concerning the design or conduct of the tests.

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At the close of the meeting, all participants agreed that staff cold shutdown j

requirements for B&W systems had been significantly clarified. B&W stated that more time was needed to complete analytical work in progress, to coordinate with B&W customers, and to establish designs compatible with both staff requirements and B&W needs.

Thones R. Cox, Project Manager Standardization Branch Division of Project Management

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Enclosures:

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Attendance List 2.

Presentation Material

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,f-ATTENDANCE t 'SJ Date of meeting: 7-27-78 9

Facility: BSAR-205 Docket No. STN 50-561 NAME ORGANIZATION T. Novak DSS /NRC T. Cox DPM/NRC V. Benaroya DSS /NRC S. Burwell DPM/NRC S. Newberry DSS /NRC W. LaFave DSS /NEC L. Riani DSS /NRC D. Fischer DSS /NRC F. Orr DSS /NRC C. Stahle DPM/NRC C. Graves DSS /NRC

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DPM/NRC A. Bournia s _,

S. Israel DSS /N3C D. Tibbitts DPM/NRC J. H. Taylor B&W M. Maarhoff VEPCO s

D. Batalo VEPCO E. Swanson B&W D. Newton B&W D. Lee B&W H. Fortune B&W K. Lingappan United Engineers D. Wilson Tannessee Valley Authority D. Terrill T7A J. Moran PASNY J. Zabritski CPCo 1-*"

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ENCLOSURE 2 B&W PRESENTATION MATERIAL

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NRC SAFE SHUTDOWN POSIT 10f4 A.

OLD POSITION l

ACHIEVE AND t%INTAIN HOT SAFE SHUTDOW

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POTENTIAL FOR C00LDOWN USING ANY A 2.

EQUIPMENT WITH NO LOOP OR SINGLE ACT

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FAILURE.

B.

NEW POSITION ACHIEVE AND MAINTAIN HOT SAFE SHUTDO 1.

CAPABILITY TO ACHIEVE AND MAINTAIN COL 2.

SHUTDOWN USING SAFETY GRADE EQUIPM l

i ASSUMING A LOOP AND A SINGLE ACTIVE) i i

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l E BASIS FOR SAFETY GRAT COLD ShilTinN D ALTEGI HSSD IS A S.VE CCDITIQi, CSSD IS nutras.

"HE-1@ CCSIERS IT ECEPTA21.E TO EFAIN AT OR I

EAR t0fM. TEFATItE TBfEPATUE #0 PESSUE FOR EXTENDED PERIODS & TIE."

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PESSWE #0 TEITEPATUE C00lTIOS ASSOCIATED WITH I

@El%TIGl 0F TE DiRS IS PFutFJts 40 ItH5ENR.Y i

PPD /IES ADDITIQlAL SYSTEM MIIO! CMI E USED IN PEFEEN TO LGE tem C00LItG AT HIGi TEMBATUES f

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2) EERIAL C00UD!l PAY E E0]IED FOR EPAIRS, INSPETIGS ETC.

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" TEE t%Y E #1 'EWIT' TPAT EWIES EWmjAL C01DGN TO EMIT EITER I.0E-TER C00Ll?E WITH TE DiRS OR INSPECTIGE #S EPAIRS."

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NRC COLD SAFE SHUTDOWN DESIGN REQUIREMENTS i

GENERAL C00LDOWN THE Pt. ANT USING ONLY SAFETY GRADE EQUIPMENT ASSUMING A LOOP AND A SINGLE ACTIVE I

FAILURE.

DETAIlFD 1.

PROVIDE SAFETY GRADE MAD VALVES, OPERATORS, AIR AND POWER SUPPLIES.

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2.

C00LDOWN CAPABILITY IN LESS THAN 36 HOURS I

ALLOWING. NUAL AND CORRECTIVE ACTIONS.

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PROVIDE SEISMIC CATEGORY I AFW SUPPLY FOR 4 HOURS HOT PLUS C00LDOWN TO DHRS CUT-IN.

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DEPRESSURIZE CAPABILITY ALLOWING MANUAL l

AND CORRECTIVE ACTIONS.

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B0 RATION CAPABILITY ALLOWING MANUAL AND i

CORRECTIVE ACTIONS.

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CONDUCT TESTS FOR NATURAL CIRCULATION AND BORON MIXING.

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PROVIDE PROCEDURES.

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MEETING SUM 4ARY DISTRIBUTION Docket File NRC

Participants:

NRC POR T. Novak TIC V. Benaroya NRR Reading S. Burwell SB Reading S. Newberry H. Denton W. LaFave R. S. Boyd L. Riani W. Gamill

0. Fischer D. B. Vassallo F. Orr J. Stolz C. Stahle R. Baer C. Graves i
0. Parr A. Bournia S. Varga S. Israel L. Crocker D. Tibbitts
0. Curtchfield F. Williams R. J. Mattson R. DeYoung D. Muller T. Cox Attorney, ELD

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J. Wilson

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Babcock & Wilcox Company (B&W)

UBJELI:

SUMMARY

OF JULY 28, 1978 MEETING ON RESOLUTION OF ISSUE CONCERNING ACHIEVEMENT OF COLD SHUTDOWN USING SAFETY GRADE EQUIPMENT

Background

Tne BSAa-205 Preliminary Design Approval and Safety Evaluation Report

"'UREG-0433) were issued on May 31, 1978. These documents require that the cold shutdown issue be addressed by B&W in the post-preliminary design appro-

.al period, and that applications referencing the BSAR-205 design provide design criterio and designs that are cons. stent with the requirements for the

?SAR-205 design. The BSAR-205 Safety Evaluation Report identified seven re-auirements applicable to the BSAR-205 design and the designs of the balance-of-alant portions of applications referencing BSAR-205.

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At a meeting on Jt.ne 16,1978, B&W ar.1 the staff discussed the.taff.

equirements and B&W's views on those req irements. On June 28,1978, B&W

,et wit.. their clients to discuss the staff requirements and potential solt,-

ions thereto. Subsequent to their June 26 meetina with the B&W owr.er 's emon, B&W met again with the staff on July 28, 1978, to present B&W s curr qt status of plans to comply with staff requirements and to receive staff connents no information transmitted by B&W at both the June 16 and July 28 mee:ings.

in atter. dance list and copies of the presentation material are attached.

.unarz J. Taylor of B&W opened the discussion by reiterating their position that um rM reduction inherent in going to cold shutdown in approximatelv l-1/2 ays, using only safety grade equipment,.ather thi.n proceeaing to ano main-toinim hot snutdown indefinitely, is not significant and is unjustified.

f U. 'lewts: ind E. Swanson presented the proposed B&W approach to meeting l

the staff rega rements expressed on page 5-21 of the staff Safety Evaluation aaort (SER). Each of the staff, requirements were discussed except item (6' l

in the SER, wmch requires certain procedures to be provided concerning cool-

own using nat 'ral circulation.

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The main points of the discussion for each item are included in following paragraphs.

1.

Safe ty-grade steam generator dump valve - D. Newton described B&W'.s valve, termed the modulating atmospheric dump valve (MADV). The valves, one for each steam generator, wili be located on the main steam line between the containment wall and the main stean isolation valve. Valves will be seisnic Category 1, air operated, with Class lE electrical control. power. B&W also stated that, for BSAR-205, the valves will be purchased to comply with the opera'oiiity assurance requirements of Regulatory Guide 1.48, to assure that the valve per-formance capability will be maintained after a safe shutdown earth-quake (SSE). Current BSAR-205 interface requirements provide for up to one-half hour of safety-grade air as the motive power supply.

B&W proposes that after the air upply is expended, the valves cocia be manually adjusted (handwheel) at the valve location.

T. Novak stated that the staf f pcsition on the current BSAR-205 design is that the number.of 11AD/ 's~is inadequate. B&W's calcula-tions indicate that if one of the two available valves was mer ically stuck closed, the plant cooldown time would be extended to a least g'~ '

several days. The staff considers diis time excessive. The staTr further questioned the effect of such-reduced cooling capacity on t.e i

\\'

capability for natural circulation in the reactor coolant loops.

v.__

Oranch will require that 411 e"e+ome T. Novak stated that the,t lea,st two MADV's' per steam generator, to B&W plants incorporate a assure adequate system cooling in the event of the inability to opea one salve. "; cl;c c t:ted that. ff..c; e pli atia...,10:;l u-naal r

c;r. tier c# the Man"'

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2.

Cooldown capacility - This d'scussion is reported under item 1 abo"9.

1 Seismic Category 1 auxiliary feedwater supply - The current BSAR-205^

requirements indicate that a supply for at least four hours operation at hot shutdown is required. Little discussion was held on th'.s requirement since the water suppif is the responsibility of a refer-encing applicant. B&W indicated that they consider that appropriate interface requirements have been specified in BSAR-205.

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Aeeting Sumn.ary x 4.

Depressurization - B&W representatives described three methods of depressurizing the reactor coolant system:

(a) using the pressurizer auxiliary spray system (b) usirg the pressurizer Electromatic relief valve (c) using the ECCS high pressure injection system to inject m

relatively cool water into the reactor coolant system. and-

- d i c. ' ; thre,6. L Cc 6 E a9 t" = '"^'

N Only (c) above will incorporate fully safety-grade equipment. B&W stated their opinion that because of the number of methods and equipment available, further analysis would show that the BSAR-205 design could be depressurizea while meeting the staff single failure reqairement and other requirements of the staff position. Staff members present tentatively agreed that the design appeared to include s

systems and equipment which, in conjunction with certain manual opera-

?

tions, would probably meet staff requirements for the 205 fuel assembly class of plants.

5.

Boration capability - D. Newton described the B&W equipment that would (3

provide for-a cold shutdown reactivity margin of 1% with all control l

roos assumed in the reactor.

T. Novak stated that the staff posi aan is (V

that ;ald shutdown must be accomplished after a postulated safe shut-dcWn. earthquake and a single active failure, and must be achieved a th one control rod assumed out of the reactor. Manual actions may be justified for the BSAR-205 clas< M plants, but the availability of non-seismic Category 1 equipur a ey not be assumed.

B&W acknowledged that th.

et design for boron addition components is such that not all con.ow :.St d be qualified to operate af ter the postulated event sequenct and assodated assumptions specified by the staff requirement. They stated that there would be three different methods available, with current design equipment, to inject the required boron, and that they expected that some upgrading of the current design would probably enable them to meet the staff requirement, assuming that appropriate manual actions would be justified. After,some discussion of the current de<;ign boron addition methods, staffg6ers agreed,that B&W could probably meet the requirement with me, design changes to existing systems.

/# l cei% mamsl sek.s *^d 6.

Natural circulation and baron mixing testing - The scope of the required tests wds discussed. Participants agreed that even the preliminary

~

design of the actual tests would have to follow conpletion of any system design modifications or planned manual actions that 'might evolve from l

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vendor and referencing applicant compl.iance with other requirements of l

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the cold shutdown position.

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