Text

8700-DEC-0248, Coping Duration for Station Blackout (Sbo)
	ML16277A120
Person / Time
Site:	Beaver Valley; (DPR- 066)
Issue date:	04/07/2003
From:	Ankney J; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	8700-DEC-0248, Rev 0
	Download: ML16277A120 (46)
	v • d • e

(Page 1 of

49)

Total Pages:

Calculation 00 Beaver Valley Power Station CALCULATION COVER SHEET RTL# A1.002D 8

Total Pages (Including Attachments):

49 Alternate Calculation D I Unit:

1 ORGANIZATION:

TITLE: Coping Duration for Station Blackout (SBO).

QA Category 00 I-SR D

II D

Ill D

F System I Bldg I Calculation No.

I Rev I Add Seismic:

Yes D No 00 36 I NIA I 8700-DEC-0248 I

0 I N/A Prepared by~

Checked by/Date Verified by/Date

.E: ~k~ey a.3 PJlv.~ PcuJw.~

Paul W. Dearborn "l/8(03 Paul W. Dearborn '-ff &/03 Approved by/Date Type of Design Verification d.1.~~ A-/~/o7 Design oo. Other D

Review K. Lynch Alternate D

None D

Cale.

CROSS REFERENCE DATA TER Nol Aoolicable DCP Nol Aoolicable Condition Report CR 02-07114 and CA-01 Engineering Memorandum EM-30633 Work Order Not Applicable Temporary Mod.

Not Annlicable Supersedes Cale, Rev Add Nol Aoolicable Suoolement Cale, Rev, Add Not Applicable Purchase Order No.

Not Aoolicable Pioe line No.

Not Applicable Cable/Racewav No.

Nol Aoalicable Computer Proqram, Rev Nol Applicable Kevwords Nol Aoolicable Referenced Drawinqs:

Not Aoolicable Eauipment Asset Nos-EIN Nol Aoolicable DOCUMENTS AFFECTED*

UFSAR Not Aoolicable Tech Soecs Not AppHcable Ooeralinq Manual Not Aoolicable BVPS Cales Not Aoolicable BVPS Dwgs Not Aoolicable DBD Nol Aoolicable Vendor Documents Not Aoolicable

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Beaver Valley Power Station Analysis 8700-DEC-0248 Rev. O Compiled by: J. F. Ankney J Fl'r Date: 04/07/03 Verified by: P. W. Dearborn fu&*

REVISION STATUS SHEET Revision Affected Number Sections Descri12tion of Revision Rev.O N/A Original issue of the calculation Page 2 of B Date: 4/a/4.3.

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Beaver Valley Power Station Analysis 8700-DEC-0248 Rev. O Page 3 of 8 Compiled by: J_ F. Ankney JFA Date: 04/07/03 Verified by: P. W.

Dearborn ~ Dale:

'-f/t(o..S INDEX ITEM DESCRIPTION 1.0 Background/Objective 2.0 Design Inputs and References 3.0 Method Of Analysis 4.0 Computer Program 5.0 Assumptions 6.0 Acceptance Criteria 7.0 Body Of Analysis 8.0 Benchmark Calculation 9.0 Results or Conclusion 10.0 Recommendation ATTACHMENTS Attachment A Nuclear Utility Group on Station Blackout Memorandum Dated October 24, 1988; Transmittal of NUMARC 87-00 Supplemental Documents (including Errata)

/

PAGE NO.

5 5

6 6

6 8

8 8

No. of Pages 4

I Attachment B Nuclear Management and Resources Council NUMARC 20 87-00. Section 3 Required Coping duration Category (for SBO)

Guidelines and Technical Basis for NUMARC Initiatives Attachment C EM 30633, Station Blackout Issue - NUMARC Initiatives 5

(Except for Section 3 of NUMARC 87-00 which did not include the errata as shown in Attachment A))

Attachment D E-mail Francis W Etzel to John Ankney 3-31-2003, Grid Related 1

Loss of Off-site Power Frequency Attachment E E-mail Douglas McBride to John Ankney 3-31-2003, Diesel 1

Generator Reliability.

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Beaver Valley Power Station Analysis 8700-DEC-0248 Rev. 0

t. f) Page 4 of 8 Compiled by: J. F. Ankney J FA-Date: 04/07/03 Verified by: P. W. Dearborn i?.w.v Date: Lf /8/03 Attachments (continued)

Attachment F Unit 1 Diesel Generator reliability and 100 start information 6

from the factory and UFSAR Attachment G Calculation Affected Document Review Checklist 1

Attachment H Design Verification Record and Calculation Review Checklist 3

Total = 41 Total Pages Including Attachments (8+41) = 49 j

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Beaver Valley Power Station Date: 04/07/03 Verified b : P. W. Dearborn 1.0 Background/Objective:

1.1 This calculation determines the Station Blackout (SBO) coping duration using NUMARC 87-00 methodology (Attachment 8). Condition Report 02-07114 identified that a previous SBO coping duration calculation was attached to Engineering Memorandum EM-30633. As stated in the Condition Report, an EM is not appropriate for documenting an engineering calculation. This calculation is being performed to officially document the SBO coping duration in a formal calculation.

2.0 Design Inputs and

References:

2.1 Nuclear Management and Resources Council (NUMARC 87-00, November 1987),

Section 3, Required Coping duration Category (for SBO). Guidelines and Technical Basis for NUMARC Initiatives. The following inputs were obtained from this document: ESW Group(1 ), Variables (b,c,h1,h2,h3,and h4) for the estimated frequency of loss of off-site power due to severe weather (SW Group), SW Group(2), off-site power design characteristic Group P2, EAC Group(C), target EOG reliability of 0.975.

2.2 10CFR50.63, "Loss of all Alternating Current Power" (Station Blackout), June 21, 1988.

2.3 Regulatory Guide 1.155, "Station Blackout", June 1988.

2.4 EM-30633, "Station Blackout Issue - NUMARC Initiatives" response.dated 4 1988.

2.5 Condition Report CR 02-07114, "BVPS Coping Analysis Should be Calculation (Not Engineering Memorandum)" dated 8-27*2002.

2.6 E-mail Francis W Etzel to John Ankney 3-31-2003, Grid Related Loss of Off-site Power Frequency.

2.7 E-mail Douglas McBride to John Ankney 3-31-2003, Diesel Generator Reliability.

2.8 NRC letter dated November 23, 1990 to Duquesne Light Company, "Safety Evaluation Related to Station Blackour 2.9

3BVT.36.2 Issue 1 Rev. 1 dated 12-20-2002, "Emergency Diesel Generator Reliability" 2.10 Unit 1 UFSAR Rev. 19. Paragraph 2.2.2.5, "Severe weather Phenomena";

Paragraph 8.3,"System Interconnections"; Paragraph 8.3.1 "Grid Stability Study";

Paragraph 8.5.2.2, "Diesel Generator Starting Reliability"; Figure 8.1 Sh 2 of 2, "Electrical one line diagram"; Figure 8.3-1, "Electrical Interconnections Switchyard

- Power Station.

3.0 Method Of Analysis 3.1 The method of determining the SBO coping duration is shown in Section 3 of NUMARC 87-00 (Attachment 8).

4.0 DESCRIPTION

OF COMPUTER PROGRAM 4.1 Not Applicable

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Beaver Valley Power Station Analysis 8700-DEC-0248 Rev_ 0 Page 6 of 8 Compiled by: J. F. Ankney.Jf"A Date: 04/07/03 Verified by: p_ W_

Dearborn #r:

{). Date: ~/9/l13.

5-0 Assumptions:

5_ 1 Not Applicable.

6.0 Acceptance Criteria:

6.1 Not Applicable.

7.0 Body Of Analysis: The page numbers below are referenced to NUMARC 87-00 7.1 Step one (Refer to NUMARC 87-00 Page 3-2): Determine the Off-site Power Design Characteristic Group_ Note that per Attachment A memorandum from the Nuclear Utility Group on Station Blackout the generic response formats have been determined by the Staff to be an acceptable means of complying with the response requirements of the Rule, 10CFR50.63.

7-2 Part 1.A Page 3-3: Determine Site Susceptibility to Grid-Related Loss of Off.

site Power Events_ The average occurrences per NUREG-1032 for the majority of systems is about once per 100 site-years. Per E-mail (Attachment D) from Francis Etzel to John Ankney the grid loss of off-site power is 1 in 31.6 years for Unit 1 and 1 in 43.3 years for Unit 2. Since BV grid related loss of off-site power frequency does not exceed once per 20 years, BV is not classified P3.

7 _3 Part 1 _B Page 3-4: Estimate Frequency of Loss of Off-site Power Due to Extremely Severe Weather (ESW)_ Use method B based upon data obtained from the National Oceanic and Atmospheric Administration (NOAA) data summarized in Table 3-2 Page 3-6_ The NRG provided this data for use by the utilities and is not required to be verified by the utility. From the table for Beaver Valley, the ESW Group is 1.

7-4 Part 1 _c Page 3-7: Determine the Estimated Frequency of Loss of Off-site Power Due to Severe Weather (SW Group). Use the following equation on Page 3-7 to determine the frequency.

f=( 1 _3*E-04 )*h1+b*h2+(1.2*E-02)h3+c*h4 Where: b=12.5 for sites with multiple rights of way i_e_ Beaver Valley c=O since Beaver Valley (BV) is not vulnerable to affects of salt spray h1 =45 for BV per Table 3-3 Page 3-9 h2=0.0000692 for BV per Table 3-3 Page 3-9 h3=0-03 for BV per Table 3-3 Page 3-9 h4=0 for BV per Table 3-3 Page 3-9 f=0.00585+0_000865+0.00036+0=0.007075 events per year Based upon the above frequency of loss of off-site the SW Group = 2 per Table 3-4 Page 3-1 O

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Beaver Valley Power Station Analysis 8700-DEC-0248 Rev. O Page 7 of 8 Compiled by: J. F. Ankney JF'A Date: 04/07/03 Verified by: P. W.

Dearborn W Date:

q/e/d3.

7.5 Part 1 D Page 3-10: Evaluate Independence of Off-site Power System.

Refer to Page 3-11. The Off-site Power System can be assigned Group l3 since "All Off-site power sources are connected to the unit's safe shutdown buses through (1) one switchyard, or(2) two or more electrically connected switchyard."

and "The normal source of AC power is from the unit main generator and there is one automatic transfer and no manual transfers of all safe shutdown buses to one preferred or one alternate Off-site power source.

7.6 Part 1 E Page 3-11: Determine Off*site AC Power Design Characteristic Group (P Group). Refer to Page 3-12 Table 3-6a for 13 sites. Using the matrix for ESW:::::1 and SW=2 the Off-site power design Characteristic Group is P2.

7. 7 Step two:

Part 2A Page 3-15: Determine the Number of EAC Power Supplies Normally Available. Since BV is a single or multi-unit site with normally dedicated power

supplies, we need to count the total number of standby power supplies normally available to the blacked-out unit's safe shutdown equipment that are not being used as an Alternate AC power source. The total number of standby power supplies normally available is 2.

7.8 Part 28 Page 3-15: Determine the Number of Necessary EAC Power Supplies.

Since BV is a single or multi-unit site with normally dedicated power supplies, we need to count the total number of EAC standby power supplies on a per unit basis necessary to operate safe shutdown equipment following a loss of off~site power.

The total number of standby power supplies necessary is 1.

Part 2C Page 3-16: Using Table 3-7 on Page 3-16 the EAC Group is determined to be C.

7.9 Step Three Page 3-16: Determine the calculated EOG Reliability. Refer to Attachment F for the original reliability tests. During the 100 start factory test, only one failure to start occurred on the first attempt for the first diesel generator set due to a pinion abutment, and no failures occurred on the first attempt for the second diesel generator. Therefore, one diesel had a 0.99 reliability and the other diesel had a 1.00 reliability. Per E-mail (Attachment E) dated 3-31-03 from the system engineer to design engineering the reliability for last diesel generator 100 starts (each diesel) has been above 97.5% for the diesels at both units. The continuing program is included in procedure 3BVf.11.36.2 and is based upon NUMARC 87-00.

7.10 Step Four, Page 3-17, Paragraph 3.2.4: Determine Allowed EOG Target Reliability. Beaver Valley has selected a target EOG reliability of 0.975 and use this target level in their reliability program. Per E-mail (Attachment E) dated 3 03 from the system engineer to design engineering the reliability for last diesel generator 100 starts (each diesel) has been above 97.5% for the diesels at both units. The program is included in procedure 3BVT.11.36.2.

/

(Page 8 of 49)

Beaver Valley Power Station Analysis 8700-DEC-0248 Rev. O Compiled by: J. F. Ankney JFPr Date: 04/07/03 Verified by: P. W. Dearborn Page 8 of 8 f ti} Date: i( Mf03.

7.11 Step Five Page 3-19: Determine Coping Duration Category. Using Table 3-8 on Page 3-19 for off-site power group of P2, an EAC group of C, and an allowed EOG target reliability of 0.975 the coping duration is 4 Hours.

8.0 Benchmark Calculation 8.1 Not Applicable 9.0 Results 9.1 As shown in the Body of Analysis, the coping duration for SBO is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

10.

RECOMMENDATION 10.1 None

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C.. ct r c * '8 7 oo - D..E.G - O Z. l/'( A-+ ~cl ~ It

~v.o NUCLEAR UTILITY GROUP ON STATION BLACKOUT SUIT'E 800 1*00 L STREET, N, W.

W""SHINGTON, 0. C. 20005*3502 MEMORANDUM TELEPHONE l202) a71*5700 October 24, 1988 TO:

NUMARC 87-00 Seminar Attendees FROM:

Michael Childers, NUGSBO Chairman SUBJ:

Transmittal of NUMARC 87-00 Supplemental Documents As you were informed at the NUMARC 87-00 seminars held earlier this year, NUMARC/NUGSBO has continued to work on several documents which support resolution of the station blackout issue and supplement NUMARC 87-00.

These documents, copies of which are attached, include:. (l} Appendix F; {2)

Appendix F Topical Report; (3) generic response format for plants using alternate AC power; (4) generic respon~e format for plants using AC independent power; (5) Questions and Answers from the NUMARC 87-00 seminars; and (6) NUMARC 87-00 Errata Sheet.

These documents have been sent to your executives along with a letter from the NRC which states that these documents provide interpretations, clarifications and methods for meeting the requirements of the station blacko.ut rule consistent with the existing ~c ~tation blackout Regulatory Guide (Reg. Guide 1.155) and NUMARC 87-00.

The t~o Appendix F documents replace the.exi.sUnq- ~PE~nC;li.l'- F *. ~ur;p:m;tl,:y fou~.d in NUliARC.. 87-00,.while

'"'"* the*--ou~st*;fcniEf*ana ;M~r~-ttt'Ooumiintt~*... serves.to.:further* 'def ihe and

.- >. int:e-rpr~~= 1115w~-'tli'ei~ 1~tl('ti,'-On.~bladicbut *rul'~ *may be*:**satisfied through

use* of "tlie~.Ni.J-MARc* :e1;.,..oo. dbciiment,,'.Items found*. in the. errata

_ :sheet**a*t~ :t!J~l:t.~ i~~-~ij:fo};~~teii i:nt6**~c a~::-oo.and th.e generic

.: response 'fo~t.s: *have )~~ri

~ determinea *by tlie Sta'ff *to. b.e an a*cceptab.le***.111.eiajl~!of:'*.cpmi;fity-ing with the* response 0requirements *of the*. rule;' 10""

0 c~~F:.R.: "§50. 6~:~J.

- . *y

\\

PleasEi*-=-t~~~***freet.to"':':caii"°'with*. any questions you* may"1-haol,e.

---.. -......n.

.~:..--*-...

(Page 10 of 49)

\\ '*-

C.u Ic. '.E "?CO 1'D ~G-tJ 2.lf'Z" A-+io.. cl, *Pr 17<'.eV', D Errata to NUM1\\RC 87-00

1.

P. 2 Section 2.s.1, should read:

OCTOBER 1988 "Sources.of expected PWR and BWR reactor coolant inventory loss include (1) normal system leakaqe, (2) losses from letdown, (J) losses due to reactor coolant pump seal leakage and (4) BWR inventory loss due to SRV cycling and ADS actuation.

Expected rates of reactor coolant inventory loss under station blackout conditions are not expected to result in core uncovering for a PWR or ~ore than a momentary core uncovering for a BWR in the four-hour time period.

Therefore, makeup systems in addition to those currently available under blackout conditions are not expected to be

, required.

As a.result, it is expected that sufficient head I

exists to maintain core cooling under natural* circulation (including reflux boiling).

2.

PP. 2-12, 2 delete the last four lines on page 2-12 and the first line on page 2-13 in entirety.

3.

P. 2 Section (3) "Control Room Habitability", second paraqraph - delete the first two sentences in entirety.

(Page 11 of 49)

C. G { C, ~ '7 O~- {J EC - 6 2-tfg fl--tf QCJ h. It Errata to NUMARC e1-oo Re V

U Page 2

4.

P. 2 Section 2.7.2(3) - insert the following sentence before the last sentence:

"Additionally, it is expected that operators would act within the first hour to establish a stable independent decay heat removal mode which is a significant factor in the plant's ability to cope with a station blackout."

5.

P. 2 Section 2.11.2 - add to the end of the last sentence of the paragraph that begins "With EDG testing II "following reactor shutdown."

6.

P. 3 Table 3-Sa..:.. matrix lo.cation (SW2, ESW2) should i

read "Pl".

7.

P. 3 Table 3-Sb - matrix location (SW2, ESW2) should

'*read 11Pl"; matrix location (SW2, ESWJ) should read 11 P2*".

/

B.

P. J Table 3-6b - matrix location (SWJ, ESW3) should read "P3*"*

9.

P. 3 Part 2.B.A. -

insert:

between 11supplies 11 and "necessary" the following:

"on a per unit basis" delete:

"during a station blackout on a per unit basis."

(Page 12 of 49)

~-, 00 - DEC- 02-'fls fltf QCh* A Errata to NUMARC 87-00 Paqe 3 I@_ V'* 0 insert:

11 follo'Wing a loss of offsite power."

10. P. 3 Part 2.B.B. -

delete:

"during a station blackout for all units at the site."

insert:

"following a loss of offsite power. 11

11. P. 3 Table 3 add an asterisk after the heading "Supplies Available".

12. P. 3 Table 3 Note beginning with "Shared -

delete:

11concurrently 11 *

13. P.

~ section 3.2.3 - clarify item (1):

"(l) CALCULATE THE MOST RECENT EDG RELIABILITY FOR EACH EDG BASED ON THE LAST 20, 50, AND 100 DEMANDS (USING DEFINITIONS

, AND METHODOLOGY CONTAINED IN SECTION 2 OF NSAC-108 OR EQUIVALENT}. 11

/

14. P. 3 Table 3 The "Required Coping Duration category" on the last line should be 11 011 *

15. P. 4 Section 4.2.1(10) (d) - delete 11, as required."

16. P. 4 Section 4.3.l - strike the last sentence of item (13).

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(

GUIDELINES AND TECHNICAL BASES FOR NlJMARC INrrIATIVES

'llVMARC 87-00

3. REQUIRED COPING DURATION CATEGORY 3.1 PROCEDURE OVERVIEW This section provides a methodology for de2Z'mining the required starion blackout coping duration.

J.2 PROCEDURE Five steps are provided for d£rennining 1he requirr:d copina dur.Jtim caregay.

Step 1 Qs;tcrminc th!; OU-sire Power IGjp Cbarj!CtQjs!:ic Grmm Pbnt wcatba', pid,. and swildlyard feamres are grouped into three ca1egorics of susceplibility io losin11 off-site power labeled Pl. P2. and P3.

Srep 2 Oa..nitv !he EAC Power Supply Sy:;g CQIJfjpntiog The ~

of lhe emeraency AC power system is eva!wued and classified ammg four available groups labeled A. B, C. and D.

Step 3 Pctc:rmim: lb!! Ca!cpJa!Cd EOO Reliability 1be curm& EOO reliabiliry ii detmnined COMisltDI wilb NSAC* JOH airuia Step 4 Pmzmim di! AJlqMd EPG Ianun Rdiahiljcx B..a m c:unm: F.AC reliabilUy, 1 melhod is provided ftr deramining an acceplable

£AC mga rdiabilicy.

SU!:p S Dmpninc Copjng l)mJCion Rcqujmg:m Baed on me allowed EDG target.rdiabiliiy demmined in Siep 4, a coping duration ca11epy is calculared..

J. l

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GUID~

AND TECHNICAL BASES FOR NUMARC INnlATIVES

~L')URC 87-00 3.2.1 Slep One: Determine The Orf*sile Power Design Characteristic Group ThL objecri11e of this firsr srep is to distinguish ~rween sires hairing particular su.rcep1ibili1ia ID losing ojf-si1e power ch.u: to planJ-anJQJ!d, grid-relazed, and wearher-relaJed evuiu. Three ajf-siu power cUsign groups are pruvi.ded:

P 1 Siu.J charOJ:urizal lTy rt!dlllldmu and inkpe~nl power sources thill are col'ISidoed la.J susceplibk to loss 01 a ruulr of plans-cenlered and we.a1Jrer-WdlJJed t!ll~s:

P2 Sius whose off-me power so11nu are U!u rttlwtdam or inde~IU/QiJ, or 1ha1 are more swceprib~ to UJetuizd off-si~ puwu lo~s ~

10 weazhD'-inilimed evenJ.r or mere fr~nl loJ3a ~ID pllw-cDUUt!d nrent.r; and.

P3 Sius whose off-silt! f'OWl!r wruces are (1 J U!asr redJJniJtmJ or indepetulzrrt combined wit motkrau sevue wefllhLr porelllial, (2) mbSt susceptible ID t!Z1ended off*silt power Iossa d~ ro wea1ur*uvtiaud or srill.*rtltu~ t11tms, or (3) susceprible to gritJ-mau:d t!l'OIU..

TM3e caregorie1 are provided lTy rhL S1aff i1111ttl dro{I srlllio11 bladm11 reguiDJary guide tJNI are cUsigMd 10 be rruaually uclu.si11t. Fwnher discussion cortUrninr ~e of offsile sourcu u pravi.tUd in Section 3.3.4.

THERE ARE FIVE PARTS JN STEP ONE TO DETERMINING THE OFF-SITE POWER DE.SIGN CHARACTE.RJSTJC GROUP:

PART l.A PAR'J' 1.B PAR:rl.C PARTl.D DETERMINE THE SITE SUSCEPTIBIIJTY, TO GRJD-REU.TED LOSS OF OFFS/TE-POWER EVENTS:

ESTIMATED FREQUENCY OF LOSS OF OFF-STTE POWER DCJE TO EXTREMELY SEVERE WEATHER (.ESW GROUP):

DE1ERMJNE THE ESIIMATED FREQUENCY OF LOSS OF OFF-SITE POWER. DUE TO SEVERE WF.ATHER (S'W GROUP);

EVALUATE INDEPENDENCE OF OFF-snE POWER SYSTEM(/ GROUP):

AND, J. 2

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GUIDELINES AND TECHNICAL BASES J'OR NUMARC INITIATIVES NtruARC 87-00 PART 1.£ DE'TERMINE OFF-SITE AC POWER DESIGN CHARACTERlsrIC GROUP (P GROUP).

Part 1.A:

Determine Site SusceptibilUy 10 Grid-Related Loss or Otr-site Power Events Grid-rl!/asl!d Ion of o/J-si'6 fK1W1!r nl!nlS are defjMd tU LOOPJ thlll are srrictly rJSsociated wi1h 1he lo.rs of 1114 mmsmission and disrriblllion systl!m dll4 ro insll/ficiod genuadng capaciry, UCl!WI! loath, or dynamic inslJJbiliry.

Although grid failurl! may also ~ c11&2d by oU.U /trtan, such tu snue wmMr condi.dons or brush firts, 1.Mse eve111s are not aJnsUleml grid-l'etaud sin&1 they wae amsed ITy al67flJl nenlS.

The Wbmry average fr~ncy of grid-rW.d evenu is approzilnal41y O.OZO pe sile-yar, wilh mo.rt even1s isolated 10 a few SJSIDM. According 10 NUREG-1032, IM averaae OCCUTTl!llCt/or,,,. mJJjoriry of systems i.r aboUI OflCI! per JOO site-yl!ars. NUREG-1032 no~ ma hlzvilla afrtqUDtCy a/ grid..,e/11.ud nt!11U at rlut ona per 20 siu-ymr frtquency art!

limiwl lo St.~. T urk.q Pohrl, tutd lntHalt Poinl. Acco~gly. no miter siuJ are ~cl4d to ~ud rite Ortce per 20 site-}ffr frequmq of grill-relaud los.r of ojf-az. ~

~-

PLANTS SHOUID BE a..ASSIFIED AS P3 SllES IF l1iE EXPECIE.D FREQUENCY BASED ON PRIOR.EXPERIENCE! OP GRID*.RELA1m EVENTS EXCEEDS ONCE PER 20 YEARS. nus DOES NOT INCLUDE EVENTS Of LE.SS 1HAN S MINUTES DURATION.

EVENTS OF LONGER DURATION MAY BE EXC.UDED JP nm RESULTS Of ANALYSIS CONO.UDES lHE EVENI' IS NOT SYMPTOMATIC OP UNOERL YING OR GROWING ORIO INSTABnnY.

PUNTS C::U.SSJFIED AS Pl SrIES ON nm BASIS OP ORIO EXPERIENCE NEED NOT COMPLETE THE REMAINING PARTS OF nns S1EP IN ORDER TO.DETERMINE COPING DUllAllON REQUIREMENTS.

l - 3

(Page 16 of 49)

GUIDELINES AND TECHNICAL BASES FOR NUMARC INJTlA TIVF.S

!"JUMARC 87-00 Part 1.8: EsUmaled Frequency of Loss or Orr-site Power Due lo Extremely Severe Wealber (ESW Group)

TM esrimartd frtquot~ of loss of of!-siu powt!r due Jo t:rtnnuly JtVtrt weather is dt1enrUiud l1y tht annual e.zpecrarion of s10'7J'IJ al 1"4 sire wirh wind rdocw1 gnaur than or equal to 125 mph. These ~tnrs are l'lbrl'fl4lly associased wirh rhtt occUTren.ct of grt!fll luvricanu wf!D'e high wiluispetd..s rnay cause wifksprtrad transmission sysrem UNIYailiJbiHt'jfor wcnlkd periods. Sinctr t!~clrical distribraion ry.srems art not d4sig11td/or 1/ine conditiorzs, ir is as~d thtu rht occuTTviu af sru;lt ~t!ds will dUtrctfJ ruull in rht! lou of off-sire ]JOWtr.

USE METIIOD ft A* OR "B" Bfl.OW TO DEJERMINE TIIE ESTIMATED FREQUENCY OF LOSS OF OFF-SITE POWER DUE TO EXTREMELY SEVERE WEA'IBER AT mE SITE AND SELECT AN ESW GROUP:

A.

Site-spCciric data provides the most accunre sowco for calculating the annual freque:ocy of SIDl'JDS wilb wind velocities p.ier than or equal to 125 mph. and can be used in C21caladng the estimated freqaeaq of Jou of ofr-slle power doe to extremely severe weather.

Once the frequency (e) is calcula!Ed, use Table 3-1 ro assign the sire ro an ESW Group.

Table 3-1 EXTilEMEL Y SEVERE WEATHER GROUPS (F.SW)

ESWGBOUP ANNtJAl. WINDSPEED EXPECTA'nON i:.

125MPH 1

c 13aJM 2

1.JslM s

c la l~J 3

hlt.l

.s

c l.Ja..,

4 1.J a 10.J s

c la 10.2 5

la 10.J

~.

\\

3. 4

(Page 1 7 of

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)

/

GUIDELINES AND TECHNICAL BASES FOR NUMARC INITIATIVES NllMARC 87-00 B.

lf site data is nm readily available to perf onn this calculation, the annuaJ estimated fi'equency of loss of off-site power due to ex1remely sev~ weather may be derived from dafa recon:ted al local weaiher swiom. A11emaaively, a loss of off-sire power frequency es'limale for exlmneiy severe weather may be based on data obtained from the National Oceanic and Atmospheric Administration (NOAA). Site-specific NOAA dala u summarized io Table 3-2 along with lhe approp:iare ESW GJOup.

3. 5

(Page 18 of 49)

)

cq,{G,~ tOO -

PEC..-()2.l(~ (<QV1 0 Atta.ck* B F'j

6 o-f'2.C GUIDELINES AND TECHNICAL BASES FOR Nt'ARC ~TTIATIVES

.SL~ARC 87°00 TableJ-2 EXTREMELY SEVERE WEATIIER DATA a SlTE STORMS ESW SlTE STORMS ESW 125 MPH+

GROuP 1l5 )!PH+

GROUP ARKANSAS NUQ.EAR ON!

0.0001 I

MC>NtICEW>

0.0003 I

ARNOLD O.IXXlll 2

NINE MILE POINT 0.0001 I

BEAVER V ALlJ!Y 0.0001 l

NORnl Al'INA o.oou 4

BELlEfONTl!

O.OOll1 1

OCONEI!

0.0011

]

BlG ROCK POOO D.0001 I

OYSTER ClEEX o.oos BRAJDW(XI) 0.001

]

PAW.ADES 0.0006 2

BROWNS FERRY 0.0001 I

PALO VERDI!

0.0004 2

B!UJNSWla 0.013 s

P!ACH BOTl'OM 0.0026

]

BYRON 0.0001 I

PERRY 0.0001 I

CAUAWAY 0.0001 I

PU.GRIM 0.0061 4

CAL VERT CJFFS O.ODll POIJ'll'llBAOJ 0.0036 4

CATAWBA 0.0011 J

l'RAIRD! ISLAND 0.002

]

Cl.INION O.CXXll I

QUADcmES 0.0002 1

CDMANCfD! PE.u 0.0001 l

RANOESECD a.com 2

axnt 0.0006 i

RIVER. BEND 0.0061 4

COOf£R.

0.0014 J

ROBINSON O.OIJJ6 CRYSTAL RIVER.

0.006 4

SAlBd Q.0031 DA~B.ESS8 0.0004 2

SANC>>JOl'RE 0.0001 I

DIABLO CANYON O.DOOI l

SEABROOK O.OIJJS 4

DRESDEN 0.0001 l

S!QUOYAH 0.0007 2

PARLCY o.ooi

]

SHOREHAM 0.01 FERMI o.ooot I

saunt'IEXAS 0.012

.5 Fn7PATJUCI[

0.0001 I

STWCII!

0.017 5

RJRTCAUJOUN 0.0014

]

SUMMER.

MOl I

]

R'.>RT ST. VRAlN O.OOOI I

SURRY 0.006 4

OINNA 0.0001 I

SUSQUEHANNA.

0.0011

]

CiRAND OU1JI O.OIM 4

11DIEB MIU! ~LAND D.002 l

HAOOAMNECI 0.01 TROJAN ll.0011 l

~

G.01 1'URDY POINT O.OZ3 HAitlt Cl.Im 2

VERMClf1' YAMIEB G.OOJ4 Jl>P!CllBB O.OIDI VOOJLB O.ooo6 2

rNDIAN FCINT OJll119 -

4 WATEllPORD 0.0061 4

IJ!WAIJJEJ Q.0036 WAmBo\\R 0.0001 I

11..uAU..B O.OlllZ I

WM'*2 0.0001 I

lllUMOll"'W' o.mz l

WOCP CRl!l!I.

O.OOCD I

MAitlB y AND!!

O.OOZI J

YANIEEAOWB 0.0056 M~

0.0001 1

ZDt 0.0001 I

MillltCM!

0.012 Note (*):

NRC STAi'F PROVIDED THE DATA JN TABLE 3-2 USING CLIMATOLOGICAL SOURCES CITED IN THE REFERENCES TO THIS PROCEDURE. NUMARC HAS NOT YEJllFIED THE ACCURACY OF TlUS DATA..

3. 6

(Page 19 of 49)

_)

)

GUIDELINES A.VD TECHNICAL BASES FOR SUMARC INmATIVES

~UMARC 87-00 Part IC:

Determine the Estimated Frequency ol Loss of O"*sile Power Due 10 Severe Weather (SW Group)

Four factors are used to calcu.Jau rhz e:niMaledfreqruncy of los.r of off-sire power dut: to senre wallur:

(1)

AMJUZl U{MCrtJdon of vwwfallfor rhz.rile, in illchzs fh1J; (2)

Annual upecrorion of tanuula11 of Jt:rtrilJ fl or gnater ar zhe sire (i.e..

windspceds greaur rhan or equal to 113 milu per ho11r), in eJDllS pu JillDTt: mi/4 fh2J:

(3)

Annual upttctalion of stomu for rhz sill with wiml HlocilleJ between 75 and 124 mph [lt3J: and, (4)

AnmuzJ upec1ario11 of 1tamu 1¥Uh Jignijiconl mlt spro:J for the sire [h4/.

TMsefacton are co""1Urd Us tM folfDwilig r~}Up to ')'U/4 rhe t:nimaud frt:~fll:Y of foss of off mt: power mu I()

~

w<<JJJrer:

b b

c t:

12.J for sim willt m"1riple rigllls of way 72.J for tilu wiJlt a 1iliglt: righl of way

0. 78 if siU is vubicrabk w effects of sa/1 sprtrf 0 for Oflwr silu Sims which an: dcsamincd IO be nsceptible to the effectS of salt spray may mnmy thU simalion lhrough design or proc:edwes IO minimir.e Ibo km of oft'-sile power.

3-7

(Page 20 of

49)

)

GUIDELL'iES At'VD TECHNICAL BASES FOR NUMARC INITIATIVES

'IJ'L')IARC 87-00 DETERMINE THE ESTIMATED FREQUENCY OF LOSS OF OFF-SITE POWER DUE TO SEVERE. WEA TIIER AS FOLLOWS:

A-Der.ermine the totaJ amount of snowfall in inches which falls an chc siu: in any year. NOAA data for snowfall are provided iD Table 3*3. Label the data used as bi.

B.

Determine the expected frequency of "fl+" 1ornadoes per square mill! for the site using plant-specific dala. NSSfC daia are also provided in Table 3-3. Label lhe data ued as b2.

C.

Der.amine the upected frequency of storms with winds between 75 and 124 mph at I.be sire. NOAA data are also provided in Table 3-3. Label the data used D.

as b3.

Delenninc Lh11 e:1pected rrequency or barrlcanes and tropical storms 'lfith sfpilkaut salt spray fir die si1e. NOAA data for siaes vuJoerable ro lhe effeca of salt spr::ay ue also provided in Table 3-3. Label die data med u b4.

E.

Calculate the utt~ated lreqnenc:y of lou or otr-slte due to severe weather, f, in evenu per year.

F.

Use Table 3-4 ID determine the Se*ere Weather Group (SW Group).

3-8

(Page 21 of

49)

GUIDELINES AND TECHNICAL BASES FOR NUMARC L"ITT'IATIVES NUMARC 87-00 Table 3-J SEVERE WEATHER DAT Ah l)U (UJ M

{MJ (UJ

~

l\\JI AR.WIWN!JJWH I

Qta)6 Qlll 0

llllmllO 411 Dm11211 WI 0

AIKlD

]J DJmZS1 Q2S D

NHIYURM lltaDlll q

0 BEAVEll VAUE'f 45 iumm lllD 0

IDDl.vfl.t.

IS OJIDlla OJI a

Bal.fRM1!

DJlllZll DJll 0

emu Ollllll on a

lllGK<O:PONf lllmlll'I D.1111 0

omaam 11 O.llDIBI Gll5I 0

ll1A!DlilXIJ 111111111 llll 0

NUWl!ll UDlld QJ 0

lliOWlfJ lmT l1lllNd II.DI 0

PAUJYFD a

tamlll tU:8 0

l!i001iK1 l

llOllll OJZ a

l!AC!lllmll D

Omlllli rum 0

ilJOI

n DJmUI Qlll 0

l'IDT ll IUDDi WI D

CAU.\\'11.U Ji 0.1111111 am D

.ll.!illY a

wmm OJI CAl.'1!1?Cl.Jl'PI I

ommn QDR 0

JallTBtlal G

Q1Dllll ILi D

CAJAWIM 111111111 Ill?

0 ltillli Wiii 411 Ql1DJ71J Q.11 D

~

Ji QtllD'll Ill 0

~am llJla llJ 0

IDWlBll'EAl Q.IGlll 1111 0

l.vmlll!m D

Ulllll OJ Q

am OJllMI IU 0

JM!lllJI)

Q ILlllllSI Gii 0

)

CIXIU.

ll Ollllil II.!

0 DllllOI I

llQ1IJJ Gii 0

0.MAUl'IEI 0

OJllllJ cu I

wa:

zz rumm

°°"

D DAYISm'lll ll OJllllll Q,ll D

!AHCRlll D

oa:am 11111 a

IJAlllDl:N'TIM 0.11111111 11111 l!dDI d

o.amtl -

tu.ml a

IJllllll am

.BJlll'All amnet

~

FW"f D

a.mm am 0

SD8WI 2'

aa:amJ OJI 0

ffDI

!:I mmn am 0

SOOl'llmAI I

llllllll1 a.a 0

RTZl'A11ia Qlmlll1 OJI

~

SfUCll OlllllJ Ill!

0 mtwmf 3

ILDIG II.I a

UOll 2

1111111 a.12 0

IQl'ST.VIALI' 9

llma3 om 0

Ull I

rumlll Q.J 0

IJIOlo\\

QlllllB 1111 0

~..

wman Oll2I 0

Wl<<ICW I

1111111!11 Cllll 0

1111!iWlUlll 1'

OJllDJ mm 0

HllbllNID "11 1111111 Oii 0

"lllWI 1

GamDI.

IUI a

IWD I

lmlm llD 0

1111DPllNI' a.a CUI D

llAllll a

111111 llllD D

'l'EDDlTAICl!I

'II' 111111111

~

0 ID!Dm 11 GlllllB llDI 0

Qilll l

Gllllll QIZI D

HIJHl'llHI'

]II llllDQ Ill 0

WA1BRID 0

. Qlllllll 119 a

U:WAIHI Q

~ II.I 0

'IA.mW ID OamG2 ILi 9

WW!

11.1111111 ml W1 D

ataml2 11111 0

IJMElll JI ommB amr llllCll!l!I 21 QllllU Q2I D

MMll.UlGll ll llmlll Olli D

f.Nl!llJll 1'

lllllm Giii 0

Jm.1111 5

ll1llllD cm D

7D llllllll 1l.LI 0

7J aam.

0 Q.11 NOTE (b):

NRC STAFF PROVIDED TRE DATA IN TABLE 3.3 USING CUMATOLOCJCAL SOURCES CITED IN THE REFERENCES TO Tms PROCEDURE. NUMARC HAS NOT VERinED THE ACCURACY OJ THIS DAT A..

l* 9

(Page 22 of

49)

' )

I GUIDELINES.um TECHNIC.U. BASES FOR NT.iMARC ~

TJVES NUMARC 87-00 Table J-'

SEVERE WEATHER GROUPS CSW)

SWGllOVP ESl1MA. T'iD l'lll!Qllll'K:Y 01' LOSlil OF onrsrn; POWl!:ll 1

r

.. e.DlllJ

z

&mu r

cUI*

J Ulll s

r c4Ulllle

'Q.IDI s

r co.Im

!I 0.11 s

r Part ID:

Evaluate lodepeade111ce of Off*site Power S1stem (I Group}

TM porauial for long tblradala laR of off*si'4 power evenu can have a sigllijican1 impac1 011 sllJlion blad:oUl risk and required coping dJiradoN. Loni dlualionWOP e\\ICIUI an auocialed willl gridfailuru d.U6 ID severe weazllu contiitiolLS or 1111itflll! tnuumi.uion s,stenefllQIJ{TU. Sltona dwtaion WOP ewnu rvrd ID fJtl a.rsociaud wills IJHdfic rNitchyard feamru. Two fearuru, in ptirlkallv, arc of SfM°"1 imponanc1: (1) tM ~~ii of tM o.f!*sit<< power sowcu consrilwing w prefaral. pown-supply to 1/w slwldown busu on-nu. and (7) w power 1Ta11Sfer sclterrvs wlters 1/ze normal source of A.C ptrlttr i.J Ian.

Two planl gro,.U.gs are :spuifWl in lhU pan for clttssifying 1Ju iluerf<l.IF.S Count the mw namber of d.cd.icaral and shared standby power supplies normally available to safe shutdown equipman u each site dw are not being used as an Alr.emate AC power source.

Part 2.B Determine tbe Number ol Necesury EAC Standby Powel' Supplies T114l nunrber of EAC n/INJby pmwr suppllu rtqidndfor muion bladolll is basm on 1Jw AC loads nudtd a1 ear.h uni1 ID rtmow: dtctlJ heat (W:luding riv: heas &avrall:d 1'y AC-powetd tUcay MOI remavaJ S'/SICl'U) in ord4r 10 a&hint! and main(ain sa/t! JJmJdowm wiJll off-siu ~

IWIWlilabl11._

T~ ""11!ber of EAC sllJNlby power sollTCa MCasaFy ra o~

saf11 s/uudawn ~may be ~ss 11iati thal rtqufred for LOCA load.J.

TM nwnbu of ntctssary F.AC slalldlTJ powu sources shauUI. be dtlumiMd l1y accaUlllin1 for tilt! jndjvidual saft sluudown loalb, or Urferralfram ru siu's duisn basU/or opualills Cla.si IE AC equipmor.1 wirhaUJ off*sitt AC pqtlla'.

A.

SINGLE UNITOR MUJ.11-UNITSJJFS WITH NQRMAI.LY DEPICAJED POWEB. SUPPUES Cowu lhe ioal umber olEAC sand.by power supp~

t0 opc:r.R saf'e shutdown ~wpn:n"'dnriftg-a.Sllrion ~II *1 mm a P!l' Wiit !'¥.II. - ll~r*

t)Y; ct fer-U n I i" bQ.s. t ~~eillowl'l\\.311 \\e..r~of.o-fGc:!-ep> per e..rr-Q +'l 'l/Fft L(-l.{-03 B. MULTI-UNlI SJJE.5 wrm NORMAlJ.Y SHAHID POWEB SUpp! res Coat Iha mal munber ofEAC stmdby power supplies nea:ssary IO opeme safe shutdown equipmeni ~ Ulilliiea llls:bAH fm all 1IAiil il&'m ur- ~ G; '( (13 W ) ~ ~ ( ~ j._$ 0 + 0-~ r-te fcWe O pera:~.rro.f-o.. J1-fr t-(~tf-O). 3lS(Page 28 of49)GL'IDELINES A.~ TECHNICAL BAS~ FOR NUMARC INITlATIVES NUMARC 87*00 Part 1.C Select the EAC Power Connpration Group <°" ~[)_>. USE TIIE TABLE PROVIDED BELOW TO SELECT lHE EAC GROUP: .( ~I{ l{.)*\\ "" ~e Jfft' Table J.7 ..---------------S~H-ARE...,..,.~D--i\\N..,,.,.,,,D....-::D~ED"""""tc.,,,...AT~ED..,...------------------~~* EAC GROUP SUPPLIES NECESSARY SUPPLIES AVAILABLE FOR SAFE SHUTDOWN A A B B c c D D D D I l 2 2 3 3 2 I JOEDICATED 4 4 2DEDICATED 3 SHARED 4 5 3 2SHARED-0..SlcaUd - fDI' EAC 1WldllJ poww 11111J1Plle9 Diii Hl'IDaiJJ dl*red wtlll olller aaib Ill *.db S...nd - ror EAC 1taadbJ pcnrar mppUa ID wblcb some am11bcr an normally cap*bl* or proTfclJDI AC power t9..,. !lbaldown eqtdpmeal Id more tbao OH ualt atsUe0 -*n ZDlllJ. ~ p e r~r red-a.J Flt LI - I{ - 0 :>U UJ ol Im EAC,_er 111mn:a 11n1 nonaalJJ Dared lllDOlll aa.lb 111 a **lll*DDil idle,, lbl8 la ti.a lulal aamber ol lband aad clednlld -l'H9 for llloM eaJu at tbtr 1Ue.J.2.3 Step Three: Determine The Calcalaled EDG Rellal>iUty Tire ruW EDG nliabilil1 u II.Md in conjUMrio11 widt WI siu'J off-sill powr dt!ngn cllaracteristiu (i~ ** P J, P2. or P JJ. and w EAC Ct11f/ltpllUlion (A. B, C, or D} ID dtllDPl'liM w Wlir's re~ sztui.o11 blad-Dlll coping dluasion. The unit EDG reliabiJJr7 u c.ak""-d "1 awrafing rJw indMdJIOJ EOG nUabiliq far rlw la.rt 20. 50, tlM 100 d#rrands for ea&h machiM. Ht1Wfl10, if rlvl tow nwnbit:r of valid demaNU i.J /eu than 100 (e.g.* newly li&cnsed planr, EDGs wJUch htn-e UllJUrgoM i.nunsillc maUsuna/ICt! or a nliabiJlly nf/114'lijicasion program), tlttl £DG ~ilily fTllU 1"4 la.n 20. and 1Jiz la.st 50 if availabltt, e1>>1 be averaged and compared. to IM naluadon crluria in Scctio111.2.4. 1f the wiit"s EDG reliabilily over,,,. Ian 20 dttllUUtds i.r > 0.90, DI" > 0..94 OVU IM Ian 50 umt>>ub. then IM unit MIZ1 St!leCI an EDG lllrger rdiabilUJ of eWu!r 0.95 or 0..9'7$ a.r daraikd i.it Sttrion J.2.4. 3-16 (Page 29 of49)I I ) GUIDELINES AND TECHNICAL BASES FOR m!M.-\\RC INII1A TIVES NtMARC 87-00 T~ objecrive of tM 11tru-~r approach 10 reliobiury m11asure1'U!1t1 is ID provi/U grea1u deprh of undt:rstanding regarding reliabiliry trends. The 20-dl:mmid sample set i.s 1u most volatile, and offers a very sensitive imlicarion of £DG perfonrv:uu:e. Situ;I! UU., Uulicazor mo\\leS' wilh earh incrl!ml!nzal failure or.nu:cus. it iJ NH considered a reliable measure of long-rerm perfonNJllU. Similarly, 1"4 100-"4mand sampll! sel offer:t a ltmg*tenn trend indicarion, while providing limited Wiglil to recetU rrelllb dJll! ro do1a smoothing q/ecu. TM 50-demand :1a111p~ sel bridges 1~ rwo indicators while also providiltg an inu~ditul! l~l. Taken w1e1/wr, IM set of iNJicaJors provitlu a fairly compleu pictrue of EDG re/UJbilily. ~-0. '"!;o <"()... v_~{) ~Y' v..- oe",./-h DEJERM]NE nm CURRENT UNIT EDCj REI 'AHIIJJY* r if ' (1) CAI.a.JLATE 1HE MOST RECEm' EDO REUABll..ITY FOR EAC:l.EDG BASED ON THE LAST. 20. so, AND 100 DEMANDS (U~G~ oEmimoNS AND METHODOLOGY CONTAINED IN SECTION~ DOCUMENT OR EQUIVALENT). CALCULA'IE.lHE NUCLEAR UNIT AVERAGE EDG RELIABn.ITY FOR 1HE LASl' 20 DEMANDS BY A VFllAG:n.lG 11IE RESULTS FROM (I), ABOVE. CAl.CULA'l'E nm NUa..EAR. UNIT AVERAGE EDO RELIABILITY FOR THE LAST SO DEMANDS BY AVERAGING THE RESULTS FROM (1). ABOVE. CALCULATE 1llE NUa.EAR UNIT A VERAOE EDG RELIABD..IT'Y FOR TIIE LAST lOODEMANDSBY AVEKAGINGlllERESULTSfROM(I). ABOVE. J.2.4 Step Four: Determine AUowed EDG Tarpl ReU.biUty Tlwr minimMln EDG reliabilily sholllll b. 1a1J11U!d al 0..95 per demand per EDG far planu ill EAC Graup1 A, 8. C. allti 0.915 per dl!1naNI pu EDG /of' plaliu in F.AC Group D. 1Ms11 rdi.abilizy levds iltollld ht! considced Minimum UJrget reliabililias. Ea&Jr plaJu.rlroulil urablisll a EDG RellabiW, Provam tU 0111/Wtl in Ap,,.nda D to this tkcWMraf' Plmlu wide/I uiltt:I a 111r1a EDG reliDbililJ afO!J7J 1/to.Jd IUiliu 1/rU targel level in tlwir reliabili11 program. If IM dil!Jd geneolor ptteformanu /aJU below llw ""I., rdiabilby llrv.1 spl!Ci/U!d. action JJrouJd ht! ta.ten rhra"glr an EDG relUlbiliry FOgram sw:ll a.i 1111 fonll in~ D ro restore tlw rarger re6abi1U, Wlft. The unil EDG nfiabilily for rJw last 20, 50, tllld JOO danlWb calt:uJtuetl in dw prrtliDru stq pr<TVidl!s rhc allowed rarget reliabiliry uud in de1BmUWt1 minimum ret{llired.stiJlion bla.ck.out coping dwal:imu. ill IM n£U st4p. 3 - 17 (Page 30 of49)\\ I Gt..'IDELDfES.urn TECHNICAL BASES FOR Nli'MARC INITIATIVES'll'"L'MARC 87-00 ALLOWFD TARGET RELlABllJTIES ARE DETERMINED AS FOLLOWS:(I) COMPARE THE CALCULATED AVERAGE NUCLEAR UNTT EDG RELIABILITY DETERMINED IN SECilON 3.23 TO lHE CRITERIA BELOW: Eya!u.;Uign Crircrja LAST 20 DEMANDS > 0.90 REUABll.JTY LJ.ST 50 DEMANDS > 0.94 REllABILITY UST 100 DEMANDS > 0.9.5 REilABn.ITY (2) IF TIIE EAC GROUP IS A. B, OR C. AN.IL ANY OF THE THREE EVALUATION CRITERIA IN SECTION 3.2.4, S"reP FOUR. PART (I} ARE MET, TIIEN 1HE NUa.EAR. UNIT MAY SELECT AN EDG RELIABll.ITY TARGET OF EITHER. 0.9.5 OR 0.97.5 FOR DEIERMlNINO TiiE REQUIRED STATION BLACK.OUT COPING DURATION. IF nIE EAC GROUP IS D, AND ANY OF lHE rnREE EVALUATION CRITER.IA JN SECTION 3.24, STEP FO~ PART (l) ARE MET, TIIEN lHE All.OWED EDO RELIABil.ITY TARGET IS 0.97.5. (3) IF nm 'EAC GROUP IS A. B. OR C, AND NONE OF THE 1HREE EVALUATION CRl1'ERIA IN.SECTION 3.2.4, STEP FOUR. PART (1) ARE MET, TiffiN 0.9.5 SHOULD BE USED AS lHE RELIABIUTY TARGET FOR DETERMINING TIIE REQUIRED STATION BLACKOUT COPING DURATION. ADDmONALLY, IP THE.REUABIUJY IS LESS l1IAN 0.90 BASED ON lHE LAST 20 DEMANDS, THEN ACCEYI'ABll.JTI' OF 1HE COPING DURATION RESULTING FROM USING 0.9.5 MAY REQUIRE FUR"lllER. JUSTIFICATION. IP THE P..AC GROUP IS D AND NONE OP THE nmEE EVALUATION CR.1TERIA IN PART (I) ARE MET. lHE REQUIRED COPfNO DURATION CA~GORY CALCUI.ATED IN STEP FIVE. SECTION 3.2..5 SHOULD BE INCREASED TO 1HE NEXT HIGHEST LEVEL (I.E.. FOUR HOURS BECOMES EIGHT HOURS; EIGHT HOURS BECOMES 16 HOURS).3. 18 0(Page 31 of49)Gu1DELINF.S AND TECHNICAL BASES FOR :-<<IMA.RC INITIAnvE.s Nl'ARC 87-00 J.2.5 Slep Fin: Determine Coping Duration Category USE THE TABLE PROVIDED BELOW TO DETERMINE 1lffi COPING DURATION REQUIREMENT IN HOURS: Table J..8 ALLOWED £00 REQUIRED OFFSITE POWER. EA.C GROUP TARGET KEUABILITY COPING DURATION GROUP (Frum Sect.loo J.2.2) (Per Demml} CATEGORY ~Fr*m Seetl1111 J.l.l} (Jn* SecUom J.2.i&) Pl A 0.!150 2 Pl B 0.9.50 4 Pl c 0.9.SO 4 Pl D 0.97S 4 P2 A 0.9.SO 4 P2 B 0.9.SO 4 w -7 Pl c D.973' 4 P2 c M.SO B n* c D.9.SO 4 Pl D 0.97.Sa 1'19 D0.975 4 P3 A 0.975 4 P3 A 0.9.50 8 Pl" A 0.950 4 P3 B D.97.5 4 Pl B D.9.SO 8 PJ* B D.9.SO 4 P3 c D.975 8 PJ* c 0.91$ 4 P3 c 0.9.50 16 PJ* c 0.9SO 8 P3 D . 0.97$ B PJ* D 0.975 4DenotH site nppwle amlbauible to implemen1alion of pint specific: pre*barricaae s.bu1down requJremenlS ud procedares wlllkb pre*ide an en.. nced copi*I capablllt7 under antlcipartd hurricane coadldou..J. 2. 6 Requlnd Actloa St8p FiVrl (~cdoll J.2..5) 'Jldd.r OM of IM /011r copiltg dJJrtllitJ11 cakgorUs di.raused ill tM NRC S1a1io11 Blo.ckoui Regulasory GllW J.JSJ: IWO ltour:1,/011r ltoun, tdJltl houri, 0116./touu. Plllnu ill 1/le ~ghl IJlld 16-how CaJl!gorits shordd ~ a&lioru to r~e risJ: col'LJisunl wilh NU MARC Station Bladout lnidolive I. TiiE FOLLOWING COURSES Of ACTION ARE AVAILABLE TO REDUCE THE ASSESSED RISK OF l - 19 (Page 32 of 49) GLlDEUNES AND TECHNICAL BASES F'OR Nl.IMARC lNITIATIV&§ NU~ARC 87-00 STATION BLACK.Our: (1) IMPLEMENT ACTION TO REDUCE lHE REQUIRED COPING DURATION TO AT LEAST mE FOUR HOUR CATEGORY BY: (a) REVIEWING PUNT-SPECIFIC WEA'IHER DATA; (b) MODIFYING 1HE SWITOI)' ARD 10 CHANGE 1HE I-OROUP; AND/OR, (c) MODIFYING TI1E PLANT TO CHANGE !HE EOO CONFIGURATION; A.ND.'OR, (cl) IMPROVING EOG RELIABil..ITY. (2) INSTAU. OR UTil.JZE AN EXISTING ALlERNATE AC POWER SOURCE nl'.AT MEETS lllE CRl1ERlA PROVIDED IN APPENDIX B.3. 20(Page 33 of49)NUCLEAR ENGINEERING MEMORANOUM Syuern No_ DCP/SMfl/TEA No. Sefe1y Rel;ned OUQIJltSNe: L.l<;;HT CO... PAl\\IV EM BEAVER VALLEY POWER STATION uN1T /.,. 2. .3~ NI\\. Yes B"'" No 0 N00o FORM OJ7-~lSJ (1*851 1---=-;;__---'----~-..___-~---t----=-=-.1~~~-I MWA No, jl{ 640-01-002-001 Accoun' No ------- PAGE No. 1 OF _I_ PRIORITY NO. 5' E. M. TITLE: ClATE: .3-1-flt (5 TO, ASSl,GN!fOTOt 0 Qt--,.~~~~-~~~~~~~~~~~-M~~k~_Y.~_L_e_e~~~~~~~~__,, ASSIGl'IEO SECTION: ~ R1----s.....J.-:J-~.l.:..k:.~--'-"'~-#-<<=-~~t~~=k=*~~~~:~~-=+-~L;.&...0;,...-.....'"""'"4~+-~_,_~~-'-~--t E3 t:.('kd~r-c::=:J [~"'-'-'~:.<.U-L:>,...4-J<;'-'---"'+-~-"'-"'"-1-":..:....:....:.,.+-~-=-~...w;.:.~~...........,_____.~.....;_,,,,...,_,,~___.~'-'-':..;:...:'-"----~----t }(' ~ ~UUYJ' §:5 $1-'-!.Ll=---1"...!::P-~l--~~~~~-=i...!0!....:'----=b~P;..c__-"=:u.......i:=--:~=-=-~-"1~~~~..J..-~~~ ~ ) P1--~~~~~~~~~~~~~~~~~~~~~~~~~-~~~- ~ t* 01--~~~~~~~~~~~~~~~~~~~~~~~-----.~~~~~~~~--1 11--~-=-:=--.-...--..----.~~-H..H-flt+\\:ff-t..a-~1--i"'\\-t-f9~~~~~~~~~~~~~~~-i s~--=----------------~---------------------f Ei------*-~-~--~-------------------~~~-----iREFERENCES:ENGINEERING CtiANGE NOTICE PREPARED BY; Requiredl DYES 01'10 E.C.N. Number; EXTENSION* (Page 34 of49)<:.Q/C, ~7ot.J-0EC.-~2..4l; f::"<..\\f,,() A+f<icl.c fj* 2..o~.£"' ~ ~I /?ek y- -/; NU f1 ARC P7-o o f~._f.-,,.., J : [ Rd.1 °' $,J.,11(] Sfer One :.Aft....,..,..,e Tlie tJ((. s:f~ Ro1-t- ~Jr C~&.~n1f..,,,*.itc P J-2 6.;os-r ft._.,.t 1. A F! 3-J 'ji,... t J. (j p, J-4 Pci-.-t 1. l p_ ~-7 ~ ..... J -Re f,,.f~.,f loJJ,,/ ~ -.r.'f.e !'°"'~ = 0,,~ pi>f' /DD r:fe - :rtJfr.I £.rf...,,~f"J Frtiwf"'j oP LoJJ of ()I/. - r:fe R"""- ~ -lo E><"lft.,,.17 fev~ Weo.-H,e~ Fsw <:1.-o\\4r = I e~d,Ot>D/ {!.1-' J>t-4.,~:r-...e ~ cJi:~c. t~ ~ ....,,, '/,.f ~J J' off-r:1-e... 'Pa\\Jv\\. ""D... t -fo f ev~ IA)p,.,~ C{ '11 fh.-,1') f = ( /*] x 1i11-.J"'.J.1 + bf.I.,_ + C/.2 "-to-2 ) l.J + c.-1..y. b-= / Z,_s- -kv s:~.J 111;-rl, '>>iJttA -r.<f"-1 D/-.Jp./ t-=- 0 t., = ~~ -Az-= O,t>ooo t~ 2. "'.l:: ~.~ -r;.11. 1-J.,--. ?. 1-7 r;..ue s-J P. i- ') Tt>i~k 1-J P. 1-7 '\\.. J = ()D 0 7" ? j--~.,h ~ y -;; u. "T - If 0 7-/n r> r. fc+) ( W 6) voap = Z.. lltt,L4; Re~- t'I; Rt.I-. l4.) (Page 35 of49)R.rt I.D : f! 1-10 £.,J".. tt. I..ok/'tM4-e.. ~ oP #f -.r. *~ ( 7 ~~.. t) P. J-1/ . II j..( ~..,t I~:f. J-11 De-fe.,,.,,,.. n...1.t>ll - ~* ~ Ac ra~4!-. elur ck,.1t,-f;..,.,*.tf.*c... 6 Yo~r c p tj,..'f) P. 3 -I 2. !?2 P. 1-/J.- R~f. ('+..) ])ef,r-... *~..fj 7ht ~~ ~y l)f EA c.. p..,,,...._ Sa...;;/.~.J !l~.. 'j A ~.-1,,,1.1~ A. S'.*.. s/e. u...-f ~......Jt.* -e,1,,./ r./~. .J wi-1-4 ">t~tJ.'!J ,/-1J.*r1 t./ ~rt.._ ll ~ p..*~-~:.,., YI... ,,... ~...../- ~*tnJ"'(l E"A C .rt..-~y po._.t,;i .r7pJ:~J : ( 1_] -J-[ ~:L -TL/, 'q (611'.o 9E afi.,a)(Page 37 of49)CQ~, '8 7oa -DEC-a ~'fZ f<'<JI* o lt-H-o..c~. c f:J. s-o-f' ~ ii Pf . /l--e.f.~.,-c-(J ; \\!) u F s.l3 t< (trf,tri i'. _?.. rs J>.1-/ ~ ;, J-1.J .f'("c1.*.,,., /I. i-G-' Of l'AR Te..t./~ Z. Z -.J .ffcf~ 2. z.. 2. J-O....> A1.1~1~nf of Oc.t 2'f ~ l'lf t Sw-f-e 7° 0 ,I Co?-"J JN.-r... t-n-i /<eef,_:re~,'ttt " p..,,'.J,..,..,, 2. I "' N"'d-ec. r-llf.*/,*',y 6~"'f 5>i Ji;.f~ l?l!(.c):oCA.+- 1 2.() 0 sf! II~" t<<~ rl,.rt *.J./, w I) w.../~...., "t.. ]). c ' 2 00]" llf) NU MARC.. f?- ~o. 6k:,/e /,-~ D,..,i JieJ,,,*tJ 11v~...J .{ro;r NrJHAJ< c..f...,; f:o.f..,eJ Acl~l,.e r.1.*d sl~:l.*m IJ/&-ick*i.tT~f-L~I-IJ,.. ti,, R~1.efff..J,,, Nov. J7 f/"-e~i..,,. 11°"""'J~wti~1 c.i.~ Re.J"olAr"c.U (o"~J..; '7tic.. I??~ 'f:)'-e sf. fl, 1-Jl/IA.rh:,f..., :D~C.z. ooo t - 2.'f-'(,(Page 38 of49)~ ~ Francis W Etzel 6 ~ 03/31/2003 09:09 AM ~r*John, To: John F Ankney/FirslEnergy@FirslEnergy cc: Kevin J Lynch/FirstEnergy@FirslEnergy, Sum T L eung/FirstEnergy@F irstEnergySubject:Re: Loss of offsite power frequency~ The grid related loss of offsite power frequency is 3.16E-02/ yr (or 1 in 31.6 yrs} at Unit 1 and 2_31 E-02/ yr (or 1 in 43.3 yrs) at Unit 2. These are the plant specific values based on operating years and actual occurrences (1 in 15.8 yrs for Uhil 1, 0 in 9.93 yrs at Unit 2). If you want an overall industry value it is 2.71 E-02/yr (or 1 in 36.9 yrs), which is based on EPRI Technical Report 1000158, "Losses of Off-Sile Power at U.S. Nuclear Power Plants - Through 1999", July 2000. Bill John F Ankney John F Ankney 0313012003 09:32 PM Gentleman, To: Francis W Etzel/FirslEnergy@FirslEnergy, Sum T LeungfFirstEnergy@FirslEnergy cc: Kevin J LynchfFirstEnergy@FirstEnergySubject:Loss of offsite power frequency I am responding lo CA-02-07114-01. I need to know the grid related loss of offsite power frequency. An analysis in EM 30633 stated this to be once per 100 site years. Is this correct? It would be appreciated if I could have the response by Wednesday 4-2-03 so that I can meet my Corrective Action due dale. I am presently on the back shift for 1R15. Thank you, John (Page 39 of 49) Douglas L McBride 03/31/2003 07:28 AM To: John F AnkneylFirstEnergy@FirstEnergy cc:Subject:Re: Diesel Generator Reliabil1ty0 As per the Station Blackout program, I keep a database of EDG start demands, load demands, start failures and load failures. Per the SBO program we are required lo keep above 97.5%. Obviously, we respond to any failure and make prevent recurrence" corrective actions if they occur. I o-f- { As of today, for Unit 1, over the last 100 unit start and load demands I am counting two failures. One was the seized river water pumps. This is not really an EDG failure, but the EDG could not have ran with no river water. The second is when the 4 kv bus undervollage relay locked up and prevented the EOG from loading during the LOOP/SI lest. Again, nol an EOG failure, but it could not have loaded. As of today, for Unit 2, over the last 100 unit start and load demands I have no failures. The BVT number is 3BVT 11.36.2 if you want to review it and it is on my shelf above my desk. OLM John F AnkneyDoug, John F Ankney 03/31/2003 01:37 AM To: Douglas l McBride/FirstEnergy@FirslEnergy cc: Kevin J Lynch/FirstEnergy@FirstEnergySubject:Diesel Generator Reliability I am presently_ performing a calculation where I need to know the reliability of the safety Diesel generators. Unit 1 UFSAR gives a reliability of 0.99 along with the basis. I cannot seem to find the reliability of the Unit 2 DGs. Do you maintain a data base of lhe times the DGs do not start when tested? Is there special maintenance done to assure reliability? Could you please respond to the a~ove questions by Wednesday 4-2-03 so that I can answer a CA?Thanks, John(Page 40 of49)BVPS UFSAR UNIT 1 Rev_ 19 A review of diesel generator power and control circuits' separation by fire area has been conducted in accordance wilh IOCFRSO Appendix R to ensure lhat a single fire' will not disable both Emergency Diesel Generators_ As a result of lhis review modifications have been made to the original diesel generator control circuits; and cab/es and equipment core have been relocated to bring the diesel generator circuits into compliance with Appendix R. The mod~icalions included relocation of Emergency Diesel Generator-2 differential protection relays and fuel transfer pump relays, rerouting of Emergency Diesel Generator-1 and -2 field flash cables, and installation of isolation relays and circuit breakers to disconnect non-essential engine controls in the event of fire-induced cable faults in the affected circuits. With these modifications at least one diesel generator will remain unaffected or recoverable by operating procedure, in the event of an Appendix R design basis fire. 8.5.2-2 Diesel Generator Starting Reliability The diesel generalor set is capable of starting and accepting loads with a 0.99 reliability at the 95 percent confidence level. A diesel genera!or target reliability of 97.5 percent has been designated in accordance with the NUMARC 87-00 document entitled "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout al Light Water Reactorsw_<9.9l NUMARC 87-00 has been endorsed by !he NRC as an acceptable means of satisfying the Station Blackout Rule - 10 CFR 50.63. If diesel generator performance falls below the target reliability level specified, actions will be laken lo restore the target reliability level in accordance with guidance contained in Appendix D of the NUMARC 87-00 document. Furthermore, the diesel generator is designed for nuclear power plant service and has included in its system certain redundant subsystems and highly reliable components. I The diesel generator sets were given a 100 start test at the factory. If any two failures had occurred, the test would have to begin again_ However, only one failure lo start occurred on the first attempt for the first diesel generator set due lo a pinion abutment, and no failures occurred on the first attempt for the second diesel generator set. ~ Preoperational tests involved fast start and accepting loads per the diesel loading sequence described above. Also, al least once a month, one set will be started manually, synchronized with the system, and run for a period of time furnishing rated power to the system_ It is concluded that the diesel generators will start and accept loads based on design for nuclear service and road data given to the vendor. The diesel generator sets have been tested at the factory to demonstrate the 99 percent reliability as described above and further lo start and accept continuous load and 1/2 hr load rating_ To ensure electrical starting system integrity, the diesel generators are periodically started and exercised in accordance with IEEE Std. 308-1971.121 (Refer to Table 8.6-1). (Page 41 of49)',o!.." "i.. *,q *'. " , *r::*, Q*..,A/.* *. nE"..... ~~ -**'~" -:.., *:.; *-~.. .* :* :~". *. '** -* \\ ~.. *:cct..1 !fri :. o~"' '11.!1 ~-:-... ~. ~~r~*~**2~.:,, J~.~gQ:.fi~~j~~!-?"~Ui'.~~.'ri"~~~l*'i!!J-::: 6~*~w;~-~~~f.'~::r.1 ~... ,>u'.."~~*~.... :;J.r, V-~----~*lT~_V*T'1~~*,.... fIT-.. ~*r:-;vu~,, -1rJU:t~. 1 *:~'- '*'-.* ~sPEcTtciN °REPORT "cONT1~u~T10H:1 .:,.;~,1f: ~.,:.~ '-; ~ *** ~~ ~:,;* "::*:-~:. 1~ : ;..**-~~ *J*~~:t.*; -~ t'~ 7~:':. ~-.-;~ "'[~~~~~' 1tl*,' ~~ *~~;t~.. -r.,.t't '*.,.... * ".\\' * ~,,. *.._~~, 'ri,t..,,.1-4.. U/Lr.~7~,""' If..t. *o*o *"' u1<:0 ** o., ' "..,.1,;. *, * * * *', ";~~~11~V.-~ * ** "ii*",\\r~;~*"'l"~>':i-';1 *~~ulc~q,i*.,.,>,,;. -/:* (,'"1: I )..*I* IJ":..;I~*' ' ' " ',,.~::.. '~'1,1!*, *t /;.<..,(,. *.~~.. t,;""~1of*{"1;*,'~ft:(t'!l~~.. :~~~,!f~~:~~!;ti'*. ~.-*o FINAL REPORT,si:-~~E ~ WE.aSTER ENGINEE_R~NG :-co~~ORAtr.or.i:ri_'.j;~;;~~};k~~t~.!t.*:*~-;11;~~'.1 ai: TRIP REPORT No-l-****sHoP ouAL.ITY CONTROL"... *-~~***._,.....,r~* 1** 1* * ***.. * .... -~ *:':.**. -~~~~~~~~~ ~.:~* CLll,,.._T Du es!la Light Con:paJJy " *.,~** ... c.. "0 **,.___.,.."'j ll~NDD~/*;;;;-.;;;,-;;o;-** "* ~ 1700 I SQ.,.t"::*.:* "I I,',.,:ec:tromo.t1v.e.J~i.v.1s1Qn_Q,f'_JJ.Jm~i:.aj. Mcito_~ Co~ra~ion *".* W!.ll~\\~* ~:~:: *.:* 1*..F<?R_ f'.ULl. HEADING. SEE_~co.10: \\'-.i**~t~,;-:::*~ '".."r*:~,*:,:*. ;: ==;;=======-* . '* '*... ~ !.(*~... - WHEN 11[1"£RRINO TO A£COA09 CHE"CK_tD OR Tt=i.n WlT':"l!:BSl.D.' l~\\IT 11v"'"i:"1"Hir ;~r.i11c1111 BHO-WH OH*oco;101,.,;.-:,*,..,_;......... " ..,1. '.1' ~...~,,.*.:.*.:.. :,J.*.. .. ** "':-\\_J.. -.. ~,-*\\~~,** ~~~~** \\.. -On MS\\Y' 25, 1972_Cl~ent personnel headed by&-*. ~u.DeVoa.mlit".Vith:.tne:vmidor'*-':::*~l'"~"l-':;:,.... ::(personnel and Ml'. C;*N. Watson," District C~ef Prcaurmient.'.CN'.~ty.*Contr01.~i.Divie10nt'.'.:".,: :.of Stone and Wab~tEn" Eagineering *Corporation tor.;;he parpcJ'e. ot "1;tnE1ssing/~e~~..... :\\.\\';{-.' '.Jj. procedure on i:nit #2 or thie order.* 1~:,,-::i.. :*."*.~:-. ::...Tests were coud110ted in accord!W.c'J with the vendor'a.c."lgineeril:ig._.te:st*.. ~tfuctionir. *,.:._I.4.lb*Revia!on D.. dated 12-1... 71, We tmderste'l\\d.theee ~ructions bad.previously been*.. ;..I submitted and approved by Stone w:ad Webster."*... :: )...:.... :: *~*.. * . -)f Test -esul.ts V6r~ BB.tisfactor;;.both to tho client and.S~oLe*:and Webster.personnel".::" ",. All test. *hi. to be doc:wn.entcd. and *presented to the assigned* inspector prior* to .. : "o release fo-~ shipment. Th"" ?"!'tion or the test prooeduro vitnessed included.l~ad* testing. j*I (l/'J load nm for 1/2 hour - 2/3 load run for l/i hour end.J'ull load run fo1: 1hoW'= *. -minimum), and reliability p.roor tests of 100 con1u~cutiv~ atarts. ~ *.* *1 -'; N I \\~**.:~. Y Not.a: Prior to composition of this report, ve understand. that* the vendor "bas. ohipped "-/ 1 both*units to the *jobsite 'Without notification to this department of* their intentio:-e, 1 "t Conaequeutly no final inspection ot the units can be M.de by this departme11:t of Stone 1 I..c..ud Wob:;ter and no supporting documentation was made available to the P.Q~C. insp'ector Iassiguod.V Wo have no assurance that the aelsmio requirement!! have been met nor CaD vaI l p?'Ovid~ !!IlY ag~.::"llllCO that doCUillsnt&ry reqilii."emtlnte ~ve been met. The vc:ido:z** a Mr. Klat.~ 1 was vell a'W1U'e ot our intent.I With this report, ve theretore close our rue unless otherv.f.sq ndvised. I The testll1g on unit 2 vas vitnessed by Mr. C. N, Watson, Distriot Cbiet P.Q,c. I Division and this re.j:N~ vaa vnttGZl b,y P9tt1 Sohroet~. i i. ~,... ;;,.3 -rte~~/. A/'~;#.~. ~~e' -~~:~~1 rd<,,., /l'-""-1:1- #'.r,,r: I I* I: I. I j i I. I '"* I ! I (Page 42 of 49) 0 U..., ~ 'f--.::tf I -fE. D (J Te -'t-.s sv-I 7 tl1.. Kro-{ 1'1""" tl~ LI BV-/(,6 Tiil* ~:11bjl!1:t unil!. ar.:.*,Jl'!n1;:icd fat llULl*-~* p.iwcr plant cml'1r;cncy standhy servln* 1Jl'llh r(*qulrcs 1 hq;b uc1~r.:>*' (l( rd!Jl.i1Hcy. Tn mecc thic; r(*Qtlircmcnt, tlw~h! 11nllb :,r.~ dl!Sli~.1h:1J *Ith Cl!rt<i1ll rcdundilnl sub-systems.:;rul highly 1clt.'.lblc cc1:111C11(r.11t!:.:m<l rl'q1.irc.1 tlc.~r1'C ol ~t!'s:.lni;: n*ll i:0nu:ion tr och~r un1~!>- Inc purp.l!h' ol tl11:. 111st1*JCtH.'ll l!' Lo.tlcllne L!us spC!1..1;1"l LC!St.ing ;md doc'> n'ot r.. n.:.:>! -1ny I,ebb st r 1 n~cn' t *. s c a*qu1 remc rH s th ;it :n,1*; i:ic.1pp I i cab le tl* componcnc sJ!'.Cc..l 111 tht*sc mL."Jo.!l!. or llr.1!S this LnstruitJ*)Jl 1.1kc th.! pL.1c.e o!J~Ollil m11nufacL-1lw,;c<111"11.:;: r;r.:rrh.*f :*i 1.,1rry1n~~ oul ll!!"ll~ th<! t.lcta1l mcLlwdr. mH~rl_<if!d,,the pl.n*; *'I l.*c;.rit,n.. *'thh11.li11g th*'co:~~t<; ~I<! l~ir lll the cl1i-.crl!LJ.l'Jn o[ the l;o;., 1 l r v C::ut r<*; ll,*11:11 r 1111.nt.. J:r,hut* *'t 1111~ Spi.:1:: 10:~1! tun !*.. 1,:-,,....._ :i1ui-.L !w r*)n<:IJI te1l f:i1 -h:lt*<*l equ.lJHHC':"d.up\\)lli.'r._ -*(Page 43 of 49} ~:* ~-.;;- *' J;;t.j. *~*. -JJ~ : ***...... PART VI ~ '.:] /.' 3*,... Ji*....]~ p ~ '>.. )~j._;_\\: _*. -.I,"is.6. -7.8.. IOAD rWN (Cent lr.ucd) Cht'c:* .:-'*~wcr C.T conactl ions wtth !\\.VAR lo.idh1g. Ch CL k and r\\,:o rd 1 u lJ spl*L!d Oil I o;,cJ and l 1rJ I npccd f 1,1 l I loud. Verify '11lh all ~y:ilo?mr; -.incl c trr:o1ts l unr_L lunJrrg that t!lll:.lnr ~ill st~rt and ~ccept load. ChcLI<. c.nd re.:.::*.rd tL_r.w.c~ri. sig1v1l to wh<!r.. [ull spocd a11tl vi;-,lLagc (irst re.'.lch r.i*.ed _v~lul'S.With.'l O~'rmal l*meq:c11L)' s11irt scqmmc.c. thls time !,iUST ~lOl cK.:ued b sacomls-11 r.1.:..1.: thnn 6,;econcls M*? re<1uirud, i:.. hcck all t11na dE:lay rcl.;ys.:ind rclit:L,1s ncc1:!:0gary to meet *the fl !.l.!Cl)nd spec it lC-iH ion-R*m 't_rc.r B. slm*1l-H1ng :i [>inion.ib*Hml*nt, rcquirtnll, J s~*:ond st.ut. 1*111'1!,.. r;He::d spnccl.:ind \\'vlta~c -~-l!_Sl ~or eKLcecJ 10 i;econds. E,.;c:r.ssi\\'e ti1J1e TE:Qu. res th.:it d1c CJ ming rl'l..1y1> assoc.la tell wllh the aec::md st.:irc be d1e::kcrJ.,nd r'1-i1mP':l.1s ncr...:si;,11y rn nu*;!t the 10 r.t>.Lond rcqu1-rcmcnr. r: PART VllRELlABIL!TY PROOF TESTS J l l IJ l1.0 .2. 1-:iLh '-Counls ;et in Amom..it-JC m::.dc, unit must r.tt11t.incl,-.ccept load l 00 U'n!H*< ut 1 vc r i Uli!5. ~') I'.' rm~ r0 l.:idJ us Lmi:-n r .1 r.-. Lo bl! oi.idc; cJur:i ng clic.:sc Ler.*t s.a.b d l-:*1:11le.d [>t'r 1.100.. ~{ each.-ye 11! l minuet.iur.*t tun m101rnu.n. (h..l 0tk ;.1Hl l(<<.-1d 11nic lr*~m i::t.rrf. bl 1~n.:d (i:;('~ l'.Hl VJ, tl_l !or st:irts l thr:-*ith 'l, i~Lh, J0th, l'.'nh.:.nd Yb thnnigh 100. In i1:ld!tH*o, r..:~:-icJ 1.1m.: r1.:qu1rc.d t<1 rt:...,:*,.J.!:.~* 1 1 <o!Jecd,,nd volt<ig<L uhl!nc-~*e1 ;,r, <..h*Jtn1cnt.:i::i:ur~ H.1k.:> ~l.Htf. I - 'iO 1,..*Lth p1clcrrc~i :-.i.,n 51..1tt..:h SC:> Ln the Ne. l in: J1.1cn Iii.;, Sl - ICIOtb !-tJll~ 1n Lhc~~--2 pcstt1.:>1l-Ooly 7... b*Jrr:icu~s '-'" ;:.:1111 1\\11: m.nor flt?t .1rc\\ pe11111Lced cl1.r1n~ 100 i;u,c.c6Sl'-L" ~lart111 1~~ll('ltl!Jlf*II lhH1 Jlm1L 1s exceed*~cl, :J;;up lh~ te&t ~nd ~t~rl over ~iter ctlc~ting nc~cs~.:..ry corlcctlon5 LO enmlnJr;: rhr-il-*Jtmant 1irubll'l'll t'A: le.:..Sl '-'h-t' clurrn,.., Lhlf. r,cr H'.S ~.1 tc-sri> C;'lg!n<: r:iust noL be st.ute.d ll>r1 r11?r lot.I vi ncr. lc!. :i Lh.*n 1l h"ur::; duriur. wliJch the.unmcr::1on hl!ut('r mul't tuner Ion ilOU r1i.11111.:i111 1111 tc1n111.:lillt.tc ;1bovo LOTS 11etll.ng.fl "i>JL!urr!" d*;nn~ th'l R.-:J1abilHy Pr<J*"I Tl?~-Ls ls any failure of chc unit tO T.C.ich 10.tCcJ !lp.:,*d clnd '-'CltJ!',C \\Jlthlrl 10 !\\C\\..C*nds ;1ftC!C lllc i;c.'.lrt Sign;il. Tha n**rr11,1l tunu 1011111 1~ nr b;:.t.k up !:oys1cmR n1iJ the tcsult1n~,;lilr::is do not .;-cn:-t1r*,r(! r. l<<LL-.::-.: Ll chc iO f.t:1..J1hl. spccr..1/-.*olL;it~C 1cquil'L':r.cnt J~-rJo:>t. lt ;, *inl'. C'>CLN"J~ the: rO-*,;;;r..:11d l 1r.11t durln>? any !'llilrt, rcc.nrcJ tLJn,~ to r.:iic~ ~p1:cd.. ncl ,_;1~,1g<: i*J: 1h.1L st.Ht and ll:uson L'( 1<.llu:*.;. F.1' l 01, 16 Pnge 9 ( 1)). (D) (DJ tD) (!J J ' l itt.. L I J~, ;pe i' .F.r" I* i r ff*~* (Page 44 of49)... ;*-,I ;t,:~,.-~ '::** ~: *p_;.... !5-.*of G'1 F IJ. *t(-'7-o ~ Pf\\R1 Vll - RELI.-,l\\1L1T.'i PROOF TE5T5 U Vll'-J.!:lf I t= D & ~~ ~ {Conl.Ltiu.:>rl) 'fhc Rl'l 1.,ti1 I tr~* r(-:-:;if Tc*r~l6 m.1y I.I:! ltHt'1 ruptcd for Lhc tcpl;.:c*11"".1t 1>1 a Jr.llt'd Cil ti11.;p~n P'lll.111d lhoJ [C~lS c.nnt11i11cll rr.:rn 1.:111L (hlJlll I~ !hi.' part bl!in!~ repl;.-:.:11 h;.f\\ no~ rau,,cd a "L.11lurc" 11:: tl1d l11cd,lbcwe-A~y icpla~cmcnt parL musr be proFcrly prc*q~aliftcd Lo Lha 0 sot1iraction ol th~ Qu~ll~y C~ncrol Dep~rlmcot J.' Sho*Jld unit i.itl tc* co1npl<?T~ *1't'6t l.,bc*,c, *1c,*C-'11Hy rc!':*lre; ;.nd mod 1 I i c.at 1 ons.are t.c; be !111..,dr.111 d t ~e t i.:S t r l:pl!J L \\~ti i15 i.u l I vi.IS:a.Fa1lu1c c~~urs dur1~g Gl~rts l-50. SLa1L over Ylth SLJrt 1 ~gain.b.F~lluce o~c.urs du11ng ~tarts51-100. (D) (1) Fr.1!1*11 .Jc~*1c.1' 1& In tH.ur ::!. c.1!ntrC'l riri:.u1;:. ** nil haa no cr.nnc.ctir.11 wilh i>tun l. c ir<:.ul t :n ls iu *;oi:ncc..t 1on v1 t.*h no nm ban~ oi etarrer~. 5tatr oveT ~[ sthrl 51. (2) Fatlci.l dt:\\'ILc li!i ::i 11~1rt.; *. nm.. ;1 10 b0Lt1 Slli:t. !'>)'Sll!ms or ls aot ttic**ind<>nT. ~'* ~" nv<.r with SL.Ht J. !'ART Vl!l - l'RF.-'.illll*Mt::NT LOAD' RI.!'.~ vi broken [J!] m.:1.:.r pinH:ns ior power conncctlonsz.Check ;.JI t-lcdrtc..il c~*nnc.n1ons 1n 111suu! th:~c.1ll ~ouncc.t1on "1re llp,hc ). D1:c1~ c:r rab1n1~t!i f>hculd h*~ c:tc:n-:?rl 11~\\Hly :incl.?ll pi1ncl,;.-aid c:uvcr plod ~s 1ni.1i;t be tn pl-H.t' I,. D*.;111 \\!nt',llW ~.-.* iuif: ")°!it<'r.i, 11r.n.. *1s l*:.n h1;,,l1*: :ind 11'~-H cxr.l\\:.n~:r;ui. 5 lJr.,1ti lull!'.!.iii u:uli.1.:c*ic. llo net -'1ns1:dl dr.*iLn pl111'.~ **nil DO :;or se;,] Jr*.in.. p\\*ri111t1,!'.i* OtilHI pluL;,; ;,1e to b-:> "r.111ppr,d 10:.:-sc",1\\J:i<.o1d thcjr l~hpC... <i'-'l! '1r.1t:-. lh ii.1 n t IJ(; I I : *- 11* :, 11 ~ c 1 c.> t~ s: r ;, 1 n,,. " t!-l~menl ,.in~l 1*i!r15Lalj, (Page 45 of49)LJ 11,,-}- 4t- ( £ [J C::r ~ .!::. b .J F-ft- '{-7-0 6 Al'PENDJX "B11 Rcpo-rt of lF.EE/PES /HP[C/SC4.2C Nee ting ScptcMbcr 20, 1973 Rcli~bility Testing of Dicscl-Gcnorntor Units JB-2.0 Task Force SC4.2C is responsible for duvcloping the qualific.<1.tion testinl: requirements that llill be includcrl a~ a revision to IEEE 38.Z,, "Criteria fo-r Diesel-Generator Ur.it:; Applied as Standby ?owar __..---Supplies for Nuclear Power Genc:rnting Sti:itions". This meeting on September 20, 1973 ~as called specifically to initiate the develop-ment of on IEEE position on rcliobility testing for dicscl-sencrator standby po1"'cr supplies. In part:i.cul;:ir is the dcsi-re to develop <:. testing procedure, other than 300 successive starts, that ~ill be acceptable to the AEC. At the beginnir.g Mr. F:nrnt Rosa of the AEC c:q1lained t:hC?ir pres en:: position and requirements for reliability testing. Th~y h.::ve :relaxed on their. rcquircmcnc. fol: 99% reliability uith i'\\ 95"/, confidence f.:i.ctol;' and appurcnt:ly arc no lonBcr looking for stntistical nl::;i.bcrs 2.s a means of verifying reliability. They have accepted the Zion qua Li~ fication tests and hilve a Regulatory Guide under preparation '~hich will be similar. These tests arc as follows.1.Mare~.n Tests This tcsc. must dcmon~trac.e c.hc cap;:ibility of the unit to carry 1157. of the plant design cmer~cncy lo~d and also the cap~bility to start a motor 1/3 larger than Tcquircd by the plant dcsiin, uh Uc tl1c unit is carrying SO"!. of its r3ted load *. This test lllUSt be pcrfotmcd twice: for each unit and may be done at the factory or in the field.2.Reliability Tests Dcfor~ Criticality cc.- 100 start and lo~d te~ts ~ith no more thDn one failure arc required. The starts must be cold s:arc:s, and Ch*.! loading must be to 507. in 30 seconds and held at 50~ until tcmp~raturc cquilibriwn. r1arm JAN 15 1974.u..n. (Page 46 of49)RTL# A1.002D Calculation Affected Document Review Checklist Calculation: 8' 7r£:l-PEc - C ~ 'f X Revision: 0 Addendum: -=---- N!ft YES NO DOCUMENT/SECTION Do the Calculation Assumptions and/or Conclusions affect:1.The UFSAR? D !Bf.2.Technical Specifications? D OJ.3.Design Basis Documents? 0 Jill4.The Operating Manual?* D ~5.The Abnormal Operating Procedures?* D ~6.Emergency Procedures?* D t8.7.OST/BVT Procedures?* D (!::8.The ISl/IST Program?* D ~9.Other Plant Procedures?" 0 Ii10.Equipment Setpoints?* 0 Jll11.Other BVPS Calculations? 0 Ji(12.Vendor Calculations? 0 ~ 13 Other VTls?* D14.Equipment Specifications? D ~15.Procurement Specifications? D16.The Fire Protection Safe Shutdown Report? D ~17.The EQ Program? D 118.Any other Design Basis documents? D19.Any radiological inputs and/or D J& consequences?When these items are checked YES, list the Engineering Change Package number that will update or track the update of the affected document(s). Attach this Checklist to the Calculation to document this review.Form 1/2-ADM-2061.F03, Rev. 2

ML16277A120

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ML16277A120
Site:	Beaver Valley (DPR- 066)
Issue date:	04/07/2003
From:	Ankney J FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
8700-DEC-0248, Rev 0
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