ML20237L060

Summary of 870820 Meeting W/Nuclear Util Group on Station Blackout in Bethesda,Md Re Guidelines & Procedures Dealing W/Numarc Initiative 2.List of Attendees & Related Info Encl

ML20237L060
Person / Time
Issue date:	08/24/1987
From:	Serkiz A NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Speis T NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
REF-GTECI-A-44, REF-GTECI-EL, TASK-A-44, TASK-OR NUDOCS 8708270401
Download: ML20237L060 (16)

Text

l AUG 2 41987 i

s MEMORANDUM FOR:

Themis P. Speis, Deputy Director for Generic and Regulatory Issues Office of. Nuclear Regulatory _Research FROM:

Aleck W. Serkiz, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reac, tor and Plant S9 stems, RES

SUMMARY

OF MEETING WITH NUCLEAR UTILITY GROUP ON STATION BLACK 0UT (NUGSB0) ON USI A-44 l

MEETING DATE:

August 20, 1987 f

LOCATION:

Phillips Building 7920 Norfolk Avenue i

Bethesda, Maryland PURPOSE OF MEETING:

The purpose of this meeting was to continue discussions of guidelines and procedures dealing with NUMARC Initiative-2.

This was the 13th meeting held with NUGSB0 since the first meeting in July 1986.

ATTENDEES:

See attached attendee list

REFERENCES:

(1) Letter to NRC Chairman Palladino from J. H. Miller, NUMARC, June 17, 1986.

(2) NUGSB0 8720, " Assuring the Adequacy of Station Blackout Response Procedures - Guidelines and Technical Bases," Revision 0.0, August 10, 1987 (prepared by the Nuclear Utility Group on Station Blackout).

i (3) NUGSB0 8750, " Assessing the Ability to Cope with a Station Blackout Event -' Procedures and Technical Bases, Revision 2.0, August 10, 1987 (prepared by NUGSBO).

(4) NUGSB0 8710, " Assessment of Coping Duration Requirements, Revision 2.0, October 14, 1986 (prepared by NUGSBO).

8708270401 870824 PDR REVGP EPSNUCSB PDR

MG24 y T. Speis This meeting was a continuation of previous discussions from the August 11, 1987 and August 13, 1987 meetings.

The outcome of this meeting was:

1).

The NRC staff has provided.NUGSB0.their review comments on l

NUGSB0-8720 and -8750 (Ref.erences 2 and 3).

An exchange of views has i

taken place and the documents will be revised by NUGSB0 to account l

for the staff's concerns.

2).

Closure on Reference 4 is still outstanding.

P. Baranowsky (NRR) and l

J. Flack (RES) need to confer with S. Maloney (NUGSBO) on several outstanding questions that Maloney has.

Maloney is to contact Baranowsky next week.

3).

NUGSB0 will prepare a single initiatives document to facilitate staff I

final review and for referencing in RG 1.155.

A preliminary draft of the contents for such a document is enclosed.

NUGSB0 indicated they

{

will target August 31, 1987 for completion of such a' combined report.

l 4).

The staff and NUGSB0 discussed A-44 rule definitions of alternate AC I

i l

(AAC) power, station blackout (SB0), Q/A guidance, etc.

A copy of I

l the current rule language (labeled Enclosure 1, August 20, 1987) was provided to NUGSB0 to facilitate discussions.

Some clarifications were made and agreed to by both parties.

NUGSB0 does not agree with the staff's need for Q/A and tech spec requirements for AAC and non-safety related equipment.

Further discussions are planned for this topic.

The staff pointed out that the paragraph (e) previously proposed as i

a revision to GDC-17 has been moved into the body of the rule (10 l

CFR 50.56).

NUGSB0 questioned the need for wording related to

" maintaining containment integrity."

5).

Brief discussions were held on differences of opinion and needs related to section 1 of RG 1.155, that deal with EDG reliability and the staff indicated that further discussions are in progress internally.

The staff also indicated to NUGSB0 a willingness to reference NSAC/108 criteria and test definitions related to EDG testing for use in the calculation of EDG reliability.

9

j 1

(

l I'.

AUG 2 4 isst t

T. Speis i The next meeting was targeted'for September 11, 1987, at which time NUGSB0's l

compiled report and RG 1.155 would be discussed for the final time.

If I

agreement is reached that the NUGSB0 report meets the staff's needs, then RG 1.155 would reference (in appropriate fashion) such a report.

I Original Signed bgi A. W. Serkis s

'1 Aleck W. Serkiz, Senior Task Manager l

Reactor and Plant Safety Issues Branch Division of Reactor'and Plant Systems, RES cc:

B. Sheron W. Minners A. Thadani F. Rosa A. Rubin P. Baranowsky S. Crockett J. M. McGarry III (BCP&R)

M. Chiiders (NU)

PDR l

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OfC : DRPS: RPSIB :DRPS:RPSIB /.Wi

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..!hb._...!.____......!h__1_*......!.....______!____..____.!._____.....!.........__

DATE$08/Af87

$ 08/2//87 08/d/87 OFFICIA. RECORD COPY

Attendees August 20, 1987 NUGSB0/NRC MEETING Name Affiliation Phone Al Serkiz NRC/RES/RPSIB 301-492-7487 Steve Floyd CP&L/NUGSB0 919-836-6901 Mike McGarry BCP&R/NUGSB0 202-857-9833-Steve Maloney DEV0NRUE/NUGSB0 617-426-4550 Mike Childers NU/NUGSB0 203-665-3472 Remo Gritz FPEL/NUGSB0 305-694-3598 Charles S. Ondash DEV0NRUE/NUGSB0 617-426-4550 John Rota DEV0NRUE/NUGSB0 617-426-4550 Janak Raval NRC/SPLB 301-492-9423 Chu yu Liang NRC/SRXB 301-492-9459 Paul Gill NRC/NRR/SELB 301-492-9474 Faust Rosa NRC/NRR/SELB 301-492-9466 Dom Tondi NRC/NRR/SELB 301-492-9490 Paul Norian NRC/RES/RPSI 301-492-7112

,. o 13tJA g. 2.p7 7ndisghMM @)

PROPOSED SINGLE INITIATIVES DOCUMENT Scope The single document includes the three existing NUGSBO documents listed below and additional information concerning Initiatives 3 and 4.

" Assessment of Coping Durations Requirements"

" Assuring the Adequacy of Station Blackout Response Procedures - Guidelines and Technical Basis"

" Assessing the Ability to Cope with a Station Blackout Event - Procedures and Technical Bases" Proposed New J

Single Document

Title:

" Guidelines and Technical Dases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," NUGSBO 8700 Proposed New Single Document l

Contents:

1.

Introduction 1.1 Objective 1.2 Document structure 1.3 NUMARC Initiatives 1.4 Action Plan a

2. Baseline Assumptions 2.1 Initial Plant Conditions 2.2 Initiating Event 2.3 Station Blackout Transient 2.4 Reactor Coolant Inventory Loss 2.5 Operator Action 2.6 Effects of Loss of Ventilation 2.7 System Crosstie capability 2.8 Instrumentation and Controls 2.9 Containment Isolation Valves i

4

,4

- 3. Assessment of Coping Duration 3.1-Overview 3.2' Procedure 3.3 Supporting Information

4. Station Blackout Response Procedures-4.1 Overview 1

4.2. Operating Procedures Guidelines-4.2.1 Station Blackout Response l

Guidelines ~

j i

4.2.2 AC Power Restoration Guidelines 4.2.3 Severe Weather Guidelines 4.3 Supporting Information l

5. Cold Fast Starts

6. AC Power Availability

7. Coping with a Station Blackout Event 7.1 Overview 7.2 Coping Analysis 7.2.1 Condensate Inventory for Decay Heat Removal 7.2.2 Class lE Battery Capacity 7.2.3 Compressed Air 7.2.4 Loss of Ventilation.

7.3 Supporting Information i

9 t '

.I

~

w, 4

i

' 3-lq 1

Appendi'ces A.

Definitions B. Alternate.AC' Power. Criteria C. Sample AAC' Configurations D.

EDG Reliability Program.

1

-1 E.

References f

i l

i j

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l ENCLOSURE 1__

(sps/n.)

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.On the basis of station blackout studies conducted for USI A.44, and presente in the reports referenced above, the NRC staff has developed a draft regulatory guide entidca "SMtion Blackout.(3) which presents guidance on (1) maintaining a high W..ei of reliability for emergency diesel generators, (2) developing procedures and' training to restore offsite and onsite emergency ac power should either one or both become unavailable, and (3) selecting a plant-specific accept-able statiqn blackout duration which the plant would be capable of surviving without ep're damage. Application of the methods in this guide would result in selection of an acceptable station blackout duration (e.g., 4 or 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) de-

However, pending on the specific plant design and site-related characteristics.

l applicants and licensees could propose alternative methods to that specified in the regulatory guide in order to. justify other acceptable durations for station blackout capability.

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4 Eenferet0sta.il81.69d11h Based on the rule and regulatory guide, those plants with an already low risk from station Alackout would be required to withstand a station blackout for a

43-2.

In 650.2.[ definitions of."A..ltern. ate.,.ge..S.o.u.rc.e..".a.n.d.o.f " station blackout a.r.e.

added in the alphabetical sequence to read as follows:

650.2* Definitions "61ttratts.es.sgurgg",estas.!g.gitstn!!!Ds.eurtsat itsl.nytt.5eerst.1 bit.15

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" Station blackout" means the cornplete loss of alternating current (ac) electric power to the essential and nonessential switchgear buses in a nuclear l

power plant (i.e., loss of offsite electric power sistem concurrent with turbine tripandunavailabilityoftheonsiteemergencyacpowersystef)'. Station Black-I cut does not include the loss of available ac power to buses fed by station bat-l teries through inverters or by, alternate,ac,,sgurces,,as,,definey,ig,this,,sget!gn, no.r..d.o.e..s.it assum.e a con.c.u..rrent single.. failure or a..g.ign basis des A._. ' M A 8 :

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l lM765 4iTV 4 MMW7AbVrb /N 7NE fl/ twt OF A crK+7N#&7' Aid THf syWiQ x cuanr/oMA new 150.63 is added to read as follows: V 3.

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150.63 Loss.*of all alternating current power (a) Requirements. Each light-water-cooled nuclear power plant licensed j

to operate must be able to withstand and recover from a station blackout as defined in 150.2 for a specified duration,k-ecceedence-wi%-the-tequ4+eme+ts-l 4e-peragnph (e)-ef-General-Design-Gr4terien-lhef-Append 4x A-ef-this-partr l

l Near term operating licenses that have not beth licensed prior to [ insert the effect date of this amendment] must comply with the rule on the same schedule i

I as those plants already licensed to operate.

(b) Limitation of Scope.

Paragraphs (c) and (d) of this section do not applytothoseplantslicensedtooperatepriorto[inserttheeffectivedate ofthisamendment]ifthecapabilitytowithstandstationblackoutwas considered in the operating license proceeding and a specified duration was accepted as the licensing basis for the facility.

(c) Implementation Beterm4matien-of-Stat (en-Blackout-9wrattene Info,mation,Su bittgh For each light-water-cooled nuclear power plant (1) r licensedtooperateonorbefore[inserttheeffectivedateofthisamendment],

l the licensee shall submit to the Director of the Office of Nuclear Reactor i

Regulationby[insertadate270daysaftertheeffectivedateofthis amendment):

(1) A proposed station blackout duration to be used in detemining compliance with paragraph of-Genere+ Des 49ft Grfterien-H-of-Appendtx-A of thishfincludinga'justificationfortheselectionbasedon--

45-(A) The, availability of the nearby alternate ac power sources that are independent of the station offs'ite and onsite ac power distribution sy,s tem; l

(B) 'The reliability of the onsite.' emergency AC power sources; (C) The expected frequency of loss of offsite power; and (D) The probable time needed to restore,cffsite power; (ii) An identification of the factors, if any, that 1 mit the capability of the plant to meet the requirements of paragraph of seiteren 2d 4.M 3

if for the specified station blackout duration proposed in the response to i

paragraph (c)(1)(i) of this section; (iii) A description of the procedures that have been established for station blackout events for the duration determined in paragraph (c)(1)(i) of this section and for recovery therefrom; and g

(iv) Alistofmodificationstoequipmentandasgeistedprocedures necessary, if any, to meet the requirements of paragraph' of Griterkn -1?N6-for the specified station blackout duration detennined in paragraph (c)(1)(1) of this sectiori, and a proposed schedule for implementing the stated modifications.

{2} Alternate ac sources: Analternateac,,ggwer,sgurce{s},as,,definej,,in,150:2

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After consideration of the infonnation submitted (St [U btggla}ggy,Assgss939}!

in accordance with paragraph (c) (1) of this section, the Director, Office of Nuclear Re6ctor Regulation, will notify the licensee of Director's determination l

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1ications for compliance with paragraph (+)-of-Generel-De54p-Cr4te4 ton-47 ef-hh f this h h (d).. Implementation...Sehedw4e. fee-implement 4ms.Etw4pment.Ned4(4 eat 4ense fI) IN leeltetDiaog,@ghtggigi For each light-water. cooled nuclear power plantlicensedtooperateonorbefore[inserttheeffectivedateofthisamend-ment),thelicenseeshall,withinISO30daysofthenotificationprovidedin accordance with paragraph (c) (4) {31 of this section, submit to'the Director of the Office of Nuclear Reactor Regulation a schedule gggmitment for imple-mentinganyequipmentandassogitedproceduremodificationsnecessarytomeet the requir n)ents of paragraph Mgf C=rd Des 4p Ge44erir 17 of-Append 4*-A- . This submittel must include an explanation of the schedule and a of this . justification if the schedule does not provide for completion of the modifications within two years of th' notification provided in accordance with paragraph (c)(2) e T h e,11ge n s e e,a y d,the,N RC,s }g f f,s h a ll,gg }ga lly,gg re g,gg of this seetion. 5sbt!91t.!or_implemgg31gg,egdificatigns ary,to,cemelywithshe recuhuments of savneraph-febkr necessis 17,Sggb.

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nd ::p-h!'ity to 45:u that the core-4+-eeoled-ead-conta4* ment ict:;rf tj/ i; i

--ee4ete4:d '- th: :::nt of : :t:tior. b!::E:ut (:: d: fined-M50-&4es t ' h:1' b; ::n:is9r$(,4*-eeec' fain; -e-epecift:d durati r 'he fon.'n; fact:r: : -4he-+ tat 4ea-Meskeet dvee44on: (1) the r:dend:n:y cf the bns't: ::: rgeasy-as-- ,l... -power sorte:, (U 4he-re"di'tv-of t5: en:ito-4mereeney 'ec r:me : u :::, l We-e*pected '-::r-y ef 1 :: ef eff:it: power $0.d-44% peobatde-- S h eeeded to-reeeece effe4te-powee. q \\' 4 I Dated at Washington, DC, this day of 1067. I I For the Nuclear Regulatory Commission. ~ + l + t' Samuel J. Chilk ie ~. t N n Secretary of the Commiss(sr.j' / ], T f ( .v 1 eye underlined text indicates additional praragraph to GDC 17. 7 2 - >; i/ + a I ..r f i ih t + 4 l R a

4 1 e AUG 2 41987 l 1 DISTRIBUTION l RES Circ RES Chron DCSiNLh00C A. Serkiz P. Norian K. Kniel RPSIL R/F i 1 l e l l 1 M l i 1 .i s l I f 1 h + J';l\\ 3y a l, j t 4 91 i I' ) ., i l6 11 8s (.i h_ V e -}}