ML16277A125
| ML16277A125 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/07/2003 |
| From: | Ankney J FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 10080-DEC-0246, Rev 0 | |
| Download: ML16277A125 (45) | |
Text
{{#Wiki_filter:(Page 1 of 45) Beaver Valley Power Station CALCULATION COVER SHEET RTL# A 1.0020 Total Pages: 8 Total Pages (Including Attachments): 45 Calculation 00 Alternate Calculation D I Unit: 2 ORGANIZATION: TITLE: Coping Duration for Station Blackout (SBC). QA Category IRI I-SR D II D Ill D F System I Bldg I Calculation No. I Rev I Add Seismic: Yes D No IRI 36 I NIA I 10080-DEC-0246 I 0 I N/A
~~~'a:lr ~j~b~ PwJru.~
Verified by/Date John F. Ankney L(-1-0 3 Paul W. Dearborn ' tlJ Paul W. Dearborn Approved by/Date Type of Design Verification IRl Other D d.{~ Design Review K Lynch Alternate D None D Cale. CROSS REFERENCE DATA TER Nol Applicable DCP Not Applicable Condition Report CR 02-07114 and CA-01 Engineerini:i Memorandum EM-30633 Work Order Not Aoolicable Temporary Mod. Nol Aoolicable Suoersedes Cale Rev, Add Not Aoolicable Suoolement Cale, Rev, Add Nol Aoolicable Purchase Order No. Nol Aoolicable Pipe line No. Nol Aoolicable Cable/Racewav No. Nol Aoolicable Computer Program, Rev Not Aoolicable Keywords Nol Aoolicable Referenced Drawinqs: Not Aoohcable .. Eouipment Asset Nos-EIN Not Applicable DOCUMENTS AFFECTED: UFSAR Nol Aoolicable Tech Soecs Not Aoolicable Ooeralina Manual Not Aoolicable BVPS Cales Not Aoolicable BVPS Dwas Nol Aoolicable ' DBD Not Aoolicable ' Vendor Documents Not Aoolicable
(Page 2 of 45) Beaver Valley Power Station Analysis 1OOBO-DEC-0246 Rev. 0 Page 2 o! ~
/8/
=C=o'""'m=ile::..:d::...,;b::;,.£,.;.:-=-J.:....;.F:.. . ;*:. . :.A. . ::cn..:. :. k::;..;n=e.t. .,.:;;:J'""""t_ft----=D=a=t-=-e:'-'0=-4=--0=7=--=03::;.._.....:V-=e""'rifi=1e=d"-'b:...L..:..:_,_P-=--..:....W::...:.*-=D::..:e=a:.:...:rb::..:o:.:..;rn'-'----L-.....IC.........:D::..:a=t~e: t/ tJ.J REVISION STATUS SHEET Revision Affected Number Sections DescriQtion of Revision Rev.a N/A Original issue of the calculation
(Page 3 of 45) Beaver Valley Power Station Analysis 10080-DEC-0246 Rev_ 0 Page 3 of 8 Compiled by: J_ F_ Ankney Jf'A Date: 04-07-03 Verified by: P. W_
Dearborn ~ Date:
Lf,/fl/Jl INDEX ITEM DESCRIPTION PAGE NO. 1.0 Background/Objective 5 2_0 Design Inputs and References 5 3.0 Method Of Analysis 5 4.0 Computer Program 5 5.0 Assumptions 6 6.0 Acceptance Criteria 6 1_0 Body Of Analysis 6 8.0 Benchmark Calculation 8 9.0 Results or Conclusion 8 1Q_Q Recommendation 8 ATTACHMENTS No_ of Pages Attachment A Nuclear Utility Group on Station Blackout Memorandum 4 Dated October 24, 1988; Transmittal of NUMARC 87-00 Supplemental Documents (including Errata) 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 Frequ~ncy Attachment E E-mail Douglas McBride to John Ankney 3-31-2003, Diesel 1 Generator Reliability_
(Page 4 of 45) Beaver Valley Power Station Analysis 10080-DEC-0246 Rev. 0 Page 4 of 8 Compiled by: J. F. Ankney JW::f\ Date: 04-07-03 Verified by: P. W.
Dearborn Pl!fP Date:
'ijB/fd Attachments (continued)
Attachment F Unit 2 Diesel Generator 300 start information from the factory 2 Attachment G Calculation Affected Document Review Checklist 1 Attachment H Design Verification Record and Calculation Review Checklist 3 Total = 37 Total Pages Including Attachments (8+37) == 45
(Page 5 of 45) Beaver Valley Power Station Analysis 1OOBO-DEC-0246 Rev. 0 Com iled b : J. F. Ankne J~lt 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 B). 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 Blackour, 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 Blackout" 2.9 3BVT.36.2 Issue 1 Rev. 1 dated 12-20-2002, "Emergency Diesel Generator Reliability" 2.10 Unit 2 UFSAR Rev. 12. Paragraph 8.1.2,"Transmission System"; Paragraph 8.1.3, "Interconnection to Other Grids"; Paragraph 8.2.1.1, "Transmission Network"; Paragraph 8.2.1.2, "345 kV Switchyard"; Paragraph 8.2.1.3, "138 kV Switchyard"; Paragraph 8.2.2.1, "(Off-site power) Availability Considerations"; Paragraph 8.2.2.2, uoff-site power) Stability Considerations; Figure 8.1-1, "Bulk Power Transmission System Unit 1 and Unit 2; Figure 8.1-2, "Electrical Interconnections"; Figure 8*.3-1,"Main One Line Diagram". 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 B).
4.0 DESCRIPTION
OF COMPUTER PROGRAM 4.1 Not applicable
(Page 6 of 45) Beaver Valley Power Station Analysis 10080-DEC-0246 Rev. 0 Com iled b : J. F. Ankne J FA Date: 04-07-03 Verified b : P. W. Dearborn
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+J:;*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
(Page 7 of 45) Beaver Valley Power Station Analysis 10080-DEC-0246 Rev. O Com iled b : J. F. Ankne JfA Dale: 04-07-03 Verified b : P. W. Dearborn 7.5 Part 1D Page 3-10: Evaluate Independence of Off-site Power System. Refer to Page 3-11. The Off-site Power System can be assigned Group 13 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 1E 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. On Unit 2 2EGS-EG2-2 was tested for 300 sta~s. The diesel generator successfully Piassed the 300 start test. A total of 272 valid start and load acceptance runs were made from warm standby temperatures with only one failure to meet the acceptance criteria. A total of 30 valid start and load acceptance runs were made from normal operating equilibrium temperatures with no failures to meet- the acceptance criteria. Per the purchase order 2BV-230, no tests were run on the other diesel. Therefore, the diesel reliability was 0.996. 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 3BVT.11.36.2 and is based upon NUMARC 87-00. 7.10 Step Four, Page 3-17, Paragraph 3.2.4: Determine Allowed EDG 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
( (Page 8 of 45) Beaver Valley Power Station Analysis 10080-DEC-0246 Rev. 0 Page 8 of 8 Compiled by: J. F. Ankney Jf fl Date: 04-07-03 Verified by: P. W.
Dearborn P~ Date:
~ffiJ.
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. 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 hours.
- 10. RECOMMENDATION 10.1 None
/
(Page 9 of 45) NUCLEAR UTILITY GROUP ON STATION BLACKOUT SUITE eoo l*OO I. STREE:T, H. W. WASHIPIGTON, 0. C. Z0005-.J502. MEMORANDUM TELEPHONE lZOZI ;571-5700 October 24, 1988 TO: NUMARC 87-00 Seminar Attendees FROM: Michael Childers, NUGSBO Chairman SUBJ: Transmittal of NUMARC 87-00 supplemental Documents As you wer~ 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; {J) generic response format for plants using alternate AC power; (4) generic'response 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 blackout rule consistent with the existing NRC $tation blackout Regulatory Guide (Reg. Guide 1.155) and NUMARC 87-00. The two Appendix F documents replace the .~isti.n~* Ap:l?endix; K cur~eatl;y '.found in NlfflARC.,87-00, .while
*-*; *th~"Quist~O}\g~,~-na ;i\jj~'i~'l-'tl'OC:tiin~tif'~*~e'fves *.to *furth~i::- 'def ihe and
- :* . interpret:* .li1:iw~.~:ttt~::~tat:i,<>ri:,~plaQkbut rul~.".'may be*:"satj.sfied t.hrough
.* ': use* of th*~- NtiMARc* ~Q 7~00. docfument ~-, Items found . in the. errata .
- =sheet "a°tef t'o ~ Q~ incpijio°iiated intO'.WJMARC a"i-0.0 and the generic res'ponse :£oaa:t.si:*ha~ .b~n!*detenitfnetl *by tl1e sta'ff to b.e an .
.a*cceptable*~ lI!.e°inii; "o-f' c9ii:p;J.1r1ng with the response .requiretnents *af the*. rule,
- 10~ t:'F-.R.' §50. 6;i;;:,
*
- Please'"'f~~t-: f;~Ei';*:t~'."*cai1 -with' any questions you* mal-ha~e .
.: * - ~ ':.. : 4' .....
11 The -s~i1i'fars* were: held on. May '.25 and 2 6'. in *.was"ttlligtfm: D. c. ; on~:~µne'-~1 "and' 2 in **Dallas; . and. on Jurie~* 15' and" 16
~ in san.Fralfcisco.
(Page 10 of 45) OCTOBER 1988 Errata to NUMARC 87-DO
- 1. P. 2 Section 2.5.1, should read:
"Sources of expected PWR and BWR reactor coolant inventory loss include (1) normal system leakage, (2) losses from letdown, (3) 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 .,Jllore than a mo~_entary 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 paragraph - delete the first two sentences in entirety.
(Page 11 of 45) Errata to HUHARC 87-0D 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 11 following reactor shutdown."
- 6. P. 3 Table 3-5a ~ matrix lo,cation (SW2, ESW2) should I
read 11 Pl 11 *
- 7. P. 3-13' - Table 3-Sb - matrix location (SW2, ESW2) should
'*read "Pl"; matrix location (SW2, ESW3) should read "P2*" .
- 8. P. 3 Table 3-6b - matrix location (SW3, ESW3) should read "P3* 11 *
- 9. P. 3 Part 2.B.A. -
insert: between "supplies" and "necessary" the following: "on a per unit basis" delete: "during a station blackout on a per unit basis."
(Page 12 of 45) Errata to mJMARC 87-00 Paqe 3 insert: 11 follo111ing a loss of offsite power. 11
- 10. P. J Part 2.8.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: "concurrently".
*.~
- 13. P. 3 Section 3.2.3 - clarify item (1):
"(l) CALCULATE THE MOST RECENT EOG RELIABILITY FOR EACH EOG BASED ON THE LAST 20, 50, AND 100 DEMANDS (USING DEFINITIONS r , 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 8".
- 15. P. 4 Section 4.2.1(10) (d) - delete 11
, as required."
- 16. P. 4 Section 4.3.1 - strike the last sentence of item (13).
(Page 13 of 45) il-f 2.0 GUIDELINES AM> TECHNICAL BASES FOR NllMARCINITlATIVES ~u'MARC 87-00
- 3. REQUIRED COPING DURATION CATEGORY J. l PROCEDURE OVERVIEW This section provides a mi:thodology for determining lbe m;iuin:d swion hlad:ouc coping duration.
J.2 PROCEDURE Five su:ps ~provided for dclcrmining die rcquim:l coping dumioo Call:gOI)'! Sicp 1 Dcramioc !.be otr-sjrc Pawq Dojp Cbaragcrislic Group Pbllt weatbet, grid. and sw:iicbyard feat11n:s an:: grouped inro three caregories of suscepr:ibiliry ro losing off-silC power labeled Pl, P2. and PJ. Si:ep 2 Cl.Psifx !he EAC l'mver Sumdx Snmn Contieuntion Tbe redundan<:y of lhe emeriency AC po'Wa' sys~m is evaluared and classified among four available groups labeled A, B. C. and D. Step 3 Qescnnine Ilg Calcubrcd EOG RdiabililX The cum:ot EDG rdiabiliry is dcimnined consis1m1t wilh NSAC-108 aiiuia.. Step 4 DamnillC II>!; AUOM!d f.00 Tqer. Bc:li2bility Based m cunaia EAC rcliabilily, a mcdlod is provided f~ detr:nnining an acecprablc EAC f2rlet rdiability. p-ya udoc Cgpin& Qurarjm Rmuirwqu Based oo the allowed EDG target reliability de~ in Step 4, a coping dwation aiegory is caJculad. 3* I
(Page 14 of 45) GUIDEUNES AND n:cHNICAL BASES FOR. ?'iUMARC INITlATlVES SU~ARC &7-00 J.2.1 Step One: Determine The orr-sile Power Desi~ Characteris1ic Group T~ objecri.ve of 1his firsr srep is ID disringui.rh berween .si~s halling pmcicu/Ju su.sctpribiliries ro wsing off-si1e powu dM4 ra planl-anund. grid-relmed, and >WaJhu.,tlaud evoau. Three off-site power ~gn groups aTI! provided: P1 Silts characurizuJ '1y redundanl and indLfHndLtU {>t!Wer sources rN1J are cof!SUUrtd
~ susceptibk ID loss as a result ofplON-celflOt!d and wet11her-iniliaud ~nu; P2 Sil.es wltou off-sile power sources aTt IDs rttbuldtznJ or indtfHndLIU, or rhllr au more SMSceptibk ID UJurdi!d off-siu power losses dJU to wea1h.u-inilialed evenLr or more
./reqwnl loJia dJll8 ta plonl~entered n>elllS; and.
PJ Silu whose off* site powu sources (U"t! ( 1) 14ast redJArldaJu or indt!fHNknr combirud wir/r moderau severe weaJher po1tntial, (2) MOsr siuceptible to UJtndLd off-site Po""'tr lossu due 10 wea1lu.r-i11itilJl.t!d or grid-relaled evenss. or (3) mscepdble ro
~evaaa.
Thae caugoriu are pruvidol. by rlu. S1af/iJt 1lu. draft stJJtion blad:ma reglliaJory guitU mul are iUsign.ed 10 ~ mJJJWllly uclwiw:. Fun/tu discmsioll cOllllnUnB indtpollUn&e ef olfsile source is provU/ed in Sttlion 3.3.4. THERE ME FfVE PARTS IN STEP ONE TO DETERMINING THE OFF-SITE POWER DESIGf'J CHAflACTERJmc GROUP: PAKT I.A DF:TF.RMINE THE SITE SUSCEPTIBJUTY TO GRJD-REJATED LOSS OF OFFSIIE-POWER EVENTS; PART l..B EST1MATED FREQUENCY OF WSS OF OFF..sITE POWER DUE TO EXIREMELY SEVERE WEATHER (ESWGROUPJ; PAKTl.C DETERMINE THE ESIJMATED FREQUENCY OF WSS OF OFF-SITF. POWER. DUE TO SEVERE WEATHER (SW GJlOf./P); PART 1.D EVALUATE INDEPENDENCE OF OFF-SITE POWER SYSTEM (I GROUP}; AND.
- 3. 2
(Page 15 of 45) (_Q.{C. r 0 o~o- ... pe.c- c z'f /, R(?.. v. 0 GUIDELINES AND TECHNICAL BASES FOR NUMARC INIT1A TIVES NID-IARC 87-00 PART l .E DETERMINE. OFF-SUE AC POWER DESIGN CHARACTEJUSTIC GROUP (P GROUP). Part LA: Determine Sile Susceptibilily 10 Grid-Related Loss of Off-site Power Eveius Grid-rt:lartd loH of o./f*sitt: power evenu OTe defined as WOPs rhal are srrictly associmed w;rh ilu! loss of rhe rran..rmission and dUtribwion systf!m d1'.e ro ;nsufficioll gtllD'cuing capacity. uctuivt: loads, or dyllllmic ins1abrliry. Alrhough gridfail11re may also be ca&sal fry orltof~ron, mt:h tU Se>Nrt! wt:al~r coftdjQon.s or l!rushjirt!S, these events art: Ml cofUUJued grid-refaud since 1Jiey weTe caasal lTj aurna1 t!VOJLS. Tiu! indusuy average freqwnq of grid-rel.aud ~ i.J apprmbnalely 0.020 pq siJe-~. wifh mosr ~Blls isolated to a few :rysrems. According to NUREG-1032, IM average occurrt!ncefor the majorisy of systems is aboYI once per JOO sil.t!-years. NUREG-1032 note:i si£u .lidving afreqiwu:y <f grid..,.t:/IJ#d ~ ar IM once per 20 n*~-year frequcicy are lirnirecl to St. /..JJ.cU, Turi.ey Poisu, and. llltllUui Point. Acc~gly, no OIMr .Dia art: apecred 10 UJ:et!d IM Once ,ur 20 ri~--year fre~n&y of grid-relmed lou of of/-sb4 powu l:1'0U.J. PLJ.NTS SHOULD BE C1ASSIFIED AS P3 SrIBS IF TIIE EXPECTED FREQUENCY BASED ON PRJOR EXPERIENCE OF GRID-RELATED EVENTS EXCEEDS ONCE PER 20 YEARS. TIDS DOES NOT INO..UDE EVENTS OF LESS 1HAN S MINUTES DURATION_ EVENTS OF LONGER DURATION MAY BE EXO..UDED IF 1HE RESULTS Of ANALYSIS CONO..UDES TIIE EVENT IS NOT SYMYI'OMATIC OF UNDERLYING OR GROWING GRID .INSI'ABIUTY. PI.ANTS a..ASSlFIED AS P'J SITES ON THE BASIS OF GRID EXPERIENCE NEED ~OT COMPLETE TIIE REMAINING PARTS OF lHIS SlEP IN ORDER TO.DETERMINE COPING DURATION REQUIREMENTS_ J- l
(Page 16 of 45)
'f o-P z.c GUIDELINES AND TEOINICAL BASES FOR NUMARC INITIATIVES :'.llt.'MARC 87-00
------~------- ------------------
Part 1.8: ~th11a1td Frequency or Loss or Off-site Power Due 10 Extremely Severe Weather (ESW Group) The utima1ed frequmt:y of loss of off-sitt powt:r d1U 10 utnnuly Jl!*l!1T wcalher i.r deremrilted by rhe (lnnual e:zpu1arion of s1orms al rhc sirl! wirh 1t1ind rel<<ilU.r gnaier than or equal ta 125 mph. These events are rwmwJly associaUd wfrh Uri! OCCUTrort! of grUJJ Ju.uricanu whoe mg/r windspeeds may cause wiiUspread rransmi.ssion sysrem unavaj}abiliry for utendd paiod.r. Since declrical disrrib1Alia11 systelrU are""' iUsigudfor 1/rese condirions, i1 i.r as~d tlw rite oci:urtt11ce ofS11Cn windspl!eds will direcrly ruull iii r/re loss uf off-sile power. USE METHOD* A* OR ~a* BELOW TO DETERMINE 1lIE ESTIMATED FREQUENCY OF LOSS OF OFF-SITE POWER DUE TO EXTR.EMEI...Y SEVERE WEATIIER AT THE SITE AND SELECT AN ESW GROUP: S_ite*spKmc data provides the most accurare soura: for calculating the annual freqaenq" of sr.onm wirll wiDd velocities gRalcr than or equal ro 125 mph. and an be
\ used la calc:uladng the estlmatfll frequency of loss of orr-sue power due I
lo enremely senre weather. Once lhe fnqumcy (e) .is calcul.am:I, use Table J-1 ro assign dle sire to an ESW Group. Table 3-1 EXTREMELY SEVERE WEATHER GROUPS (F.SW) ESWGROUP ANNUAL WINDSPEED EXPECTATION i1:, WMPH I
- c 13aJM 2 1311JM .s I c 1111..J l II 1-.l s I c 1Jal..J 4 1J
- 10.J s
- c l:s 10-1 5 l 1110-1 s
- 3- 4
(Page 17 of 45) GUIDELINES AND TECHNIC.\L BASES FOR NUMARC INITIATIVES N1JMARC87~ B. If site da1a is nor readily available to perform !his calculation, !he annual ~tim:ued frequency of loss of off-si~ power due io cx.i:remely severe weather may be derived from data n:corded at. local weama slalions. Alienwivcly. a 1055 of off-site power frequency estimare for ex.iremely severe weather may be based on data obtained from i:he National Oceanic and Armospheric Administration (NOAA). Site-specific NOAA data is summ.ariud in Table 3-2 along with the 3PPIQPriau: ESW Group. 0
..)
- 3. s
(Page 18 of 45) C q { C * ( 0 0- '[G ... ID E. C. - C 2 '( b .f<'<. V *, 'tJ 1tt+o. c-l . 8 F:J r 6 c-P 2-0 GUIDELINES A..'VD TECHNICAL BASES FOR NU~AR.C ~lTIATTVES .SU:\IAR.C 87-00 TableJ-2 EXTREMELY SEVERE WEATIIER DATAa SITH STORMS ESW SITE STOJlMS ESW 11! MPH+ GROUP ll.5 MPH+ GR.OUP ARL\NSAS NUOJ!AR ONE 0.000'2 l MONTICEUD OJJll03 l ARNOlD llOOOI 2 NINE MUPOINf OJlllOI I BEAVER VAllEl 0.0001 I NORTIIANNA 0.0014 4 BEUJ:roNrE 0.0001 I OCDNEE 0.0011 J. BIO ROCK POINT 0.0001 l OYSTER~ Cl.Im 4 llRAlDWCXJ) 0.001 ) PAUSADES 0.0006 2 BROWNS FERl.Y 0.0001 l PALO VERDE O.ll004 2 BR.UNSWla 0.013 s PEACH DOTroM Q.002.6 J BYRON 0.000'.Z I l'l!JUlY 0.0001 l c.ALU.WAY 0.0001 I .Pn.GllJM 0.006& 4 CALVERT aJFFS D.OO'll 4 POlllI' BEi.Of 0.0006 4 CATAWBA 0.0011 ) PIWRII! ISLAND 0.002 3 Q.Dll'ON a.am I QUAD Cl'I1E3 0.0002 I COMANClD! PEAK 0.000J I RAH<ll> SEal 0.0005 2 COOi 0.11116 2 RM;Jt BEND o.D06I 4 COOFD 0.0014 3 RCllINSCJf 0.111.Jli
')
I CRYSTAL RIVEJl 0.006 4 SALEN O.IXDI '4 DA~F3SB o.oooe 1 SANa<<Jflll! 0.0001 I DIABlO C.ANYaf 0.ooot I Sl!ABROCI[ 0.0031 4 DRESDEN OJJllOJ l SEQlJOYAH 0.0007 2 FAJU.SY O.Wl J SHOREHAM 0.01 s FERMI D.CG>I l SOU1H l'EX.u 0.012 s fm"lPAlRICI 0.0001 l srwcm 0.017 j RlRT CAUIOUN 0.0014 ) SUMMl!ll 0.0011 J RlRT sr. V1lAIN 0.0001 I SURRY 0.006 4 GML\ ILOOOI I SUSQUEHANNA 0.0011 J aRANDCiULP o.ooc 4 mRl!EMIU! ISUHD 0.00J ) llADDAMNEa. 0.01 HAIUUS HATOI O.OI G.mD9 2 T1IOJAN 11JRll!Y POINT
\l1!RMCH1' y ANKEE 0..0011 o.cm ll.003' J
s RlPI! ClEEI. O.OIDI . voon.B 0.IXI06 l OOIANPOlf'I' Q.0019 4 WAlEQIORD O.OOlill 4 KEWAllml 0.0036 4 WATI'SSAR. 0.0001 I LASAIJ.J! o.omz I WNP-1 0.0001 I UMPJUa. o.om l WOIPCREEX. O.OOOJ I MAIO! y ANll!B 0.002! l YANIE!ROWE 0.imti 4 MCXiUIRE llOlllll I ZDI 0.0001 I MIL1SltltfE 0.011 Not* (11): NllC STAFJI' PROVlDED THE DATA JN TABLE J-l USING CLIMATOLOGICAL SOURCES CITED IN THE REFERENCES TO THIS PROCEDURE. NUMARC FlAS NOT VERIFIED THE ACCURACY OF THIS DATA. J- 6
(Page 19 of 45) Pjr 7 of Z..O c.o. {(., I GUIDELINES AND TECHNICAL BASF.S FOR SUMARC INmATIVES ~L~ARC 87*00 Part JC: Determine the Estimated Frequency or Loss or Orr-site Power Due 10 Severe Weather (SW Group) Four factors ore wed ID coJculau r~ tstimaled freqrullCJ of lou of off-sire power diu ro Sl!Pert JHalhtr: (l) AJuumJ l!I('tcraJio11 of sno.,,/allfoflM sire, U. U.C/re:s fh1J: (2) A11111UJl upecration of IOnuuMJt!!I of 1otrity fl or gnater at the sire (i.e.,
'rllindspel!ds trl!fJID' rltlzn or equal ID I JJ mi1a pu hour), ill n'l!llU fMr SJ/l'IUI! mik f h2J:
(3) Allllual upecrario11 of starnu for r/re site with 1rilut vttlaeiliu bl!twt:en 75 alld 124 mp/I (h3/; and. (4) AlanuaJ apecraiW" of 1lomu wiJh signiflcanJ 1ah IPl'rlY for tire siu {114/. TM1e faeror1 an corrrbiMJ U. llie folli1wing relationship to yield rJw esdmatl!dfr~ of lou ofoff-sile powu due io
' Sl!W!n! "llll!llJlha-:
/
12 .5 for Jim willl muldple rigluJ of way b b .. 72J for mu wish a .Jilt1le rirlu ofw<iy c c
.. 0.78 if Jiu is vubwrobl.! "' l!ffecu of salt spray 0 for otJwr silu Sims which are delennincd to be sasceptible ro the effccu of salt spray imy remedy dtis simation through design. or
~ ID minjmirz die loss of off-siie power.
- 3. 7
(Page 20 of 45) GUID£1.INES A.'lD TECHNICAL BASF.5 FOR NUMARC INITIATIVES :'.111.i~fAR C 87-00 DETERMINE THE ESTIMATED FREQUENCY OF LOSS OF OFF-SITT POWER DUE TO SEVERE WEAIBER AS FOLLOWS: A Deumnine lhe total amount or snowfall ia inches which falls on the site in any year. NOAA data for snowfall am provided in Table 3-J. Label the dat.a med as hi. B. Derermine lhe expected rrequency or "ll+" tornadoes per square mile for lhe site using plant-specific data. NSSFC data m: also provided in Table 1-l. Label the data used as hz.
- c. Deu:rmine the apected l'requenq or slorms with winds between 75 and 124 mph a1. the si~. NOAA daa are also provided ia Table J.J. Label the data ~
as 1113. D. Dcll:lminc the upecled lreq*aq of h11.1Tlcaaes and tropical storms willl sigalncant salt spnJ for the site. NOAA data for sires vulnerable I IO !he effecis of salt spny iill'e also provided ill Table 3-3. Label I.be data used a i..t-E. Calc.ubte the estimated l'reqaency or lou of ofT-sile due to severe weather, f, in cvenis per year. F. Use Table 3-4 to determ.me the Severe Weather Groap (SW Group).
]- 8
(Page 21 of 45) GUIDELINES A..-..0 TECHNICAL BASES FOR NUMARC ImTIATIVES NIIMARC 87-00 Table J.J SEVERE WEATHER DAT Ab OJI ~ IQ !Iii) !WI IUI (kl! ,.., AWf'WN\JQWClll! 0111 llllrllllD 4' OJllllDI 0
' OLllld Qll
~ mm7 BUYEI l.\LlfT D
"n* aamm 0£111111 03 11111 0
IClllllWallT NllllANIA cmlB IS lllllDlll OJIDllQ tlJlll llll on 0 EURMI! BIG ilXI l'IJNT G.lllDd oal Clllll 0 0 omamn ' 11 QIDllll
' 0.11111111 0 BIAlllWD
!llOWIGPl!llT 0
4 omm Qllllm Qll amt a 0 PWWl!I PAL0\11111
*0 OJmMS Dllmlll Ill OJ?I 0
0
~ 1 O.mlll 1112 a l!MJllOl'tCll D OlUDJI OD g lllllJI n OJllllll !IOI a l!llT JI tmlll G.111 0 OWW~f )I D4lla 11111 l'!Llililll I G 11111111 Qll Cll..'ll!ll'WR'! t Olllll11J IUllZ 0 l'IMBPJal G 111111111 DJ C.W.'Mll o.a a l'ldlll LUlll II ll.IDll1D D Cll<<1Jt ' Glllllll 1111111 ~(]Ill llll 11 II 0
" lllllllt IUS D IDrAl'tlll.Pl!Al
** oma 11111 a WIJDlllD I IUllllD QJ a aa: W1lllG OJ. *O llVP.l llJll D Wlml Qll D
. cmn a
) JI 11111111 AS 11:&'1111 I ClialJI' Gal 0 amAUIWI
'l'IJSB:ll!
llAllJ)QlmM mm D
- m ti OlllllJ 11111111 111111111 11111111 DJ lll IUll m
I a a Q
!II.Bl
!AllClllll l!IJl!fAll D
Q ii 4 IUlllllZI ammJ Q4lllltl llllDIM lllld 111111 lllld ll D a 0 0 FAll.l!T D IUlDll 11111 0 RDWI lt O.lllllZft 1111 0
!ml u 1111111111 1111 a !CUllll!W a QIDml ill 0 Rl'D'lmtl
- wmn 11111
** SJUDI
- lllDllJ 0.13 RJll'CAUl:tif ll OJllJIG IU 11118 l U.12
!Oii' ST. VIAl!f .9 Imm am 0 mr I Gl1lllll OJ l'.ilMl (IAIG)CDI
- I QllDI Oii WI llQ'lllllf4.
lll!!Mi!llJID 41 JI umn ommn cum UZJ a 0 lwnultm. aaa 1J 1111 1Dll Qllllllll lM 0 I OD 0 1\llDm' QllllQ Ill 0 HAtal 0 llmlll UD D QIJllfl'TNll!! 11' lllllllD Gii a ID'!alil D Qlllllll!' ODii Q IUill! z Gaml illlWI "1Kf U'l'llUfll ll a llllllU
~
Ill QJ *a *11EIRID
*ATnW 0
ID llllllllZ lllllllGI og Ill lA5All! lJmlCl 11 GllllZD 111111111 Oii o.au 0 a llW-1 tllll'IJB n
~
1111111111 omms 1118 Qll IUlle TAMii! JI 11111111 Giii I TNlllllJI! 11' Glllll9 11118 0 11 ammll QmDll a.Ill 0
- 0.11 7JI(
- lllllB Qll a NOTE (b): NRC STAFJ' PROVTDED THE DATA IN TABLE l*l USING CLIMATOLOGICAL SOURCES CITED IN THE REFERENCES TO THIS PROCEDURE. NUMA.RC HAS N01' VERIFIED THE ACCURACY OF' THIS DAT A-J-9
(Page 22 of 45) GUID~ Ai"'iD TEOOOCAL BASES 'FOR Nl.JMARC L"ITT"IATIVES NllMARC 87*00 Table 3-4 SEVERE WEATHER GROUPS (SW) SWGllOIJP EST1MATm FRl!QVDICY OF LOU OF OIP1'5IT'lt l'O~ I r c9.91111 2 .._ s r cUIOI
] ..... "s r c-.aM 4 UIDI r c._109 lI Part lD: Evaluate ladepeadeace of Off-site Power Syslem (I Group)
The powuial for "'"' dJlrabon loss of off-sir. power el1DIU c12111'!ive a nsrrijicanl impac1 on station blad:ow risk and reqrlired copini dJuatimu. Lona dMraAon LOOP i!WllLr an dJSOdmtd llliill gridfailwu ~ to snut! wmtMT condirioris or unique lnlllSmWian SJllCllfeallll'u. Sliarur dMraliDn LOOP ew:nu rard ID~ ~d wills ~ciji& J'Witchyard feanuu. Two fearuru. ill panicular, an of ~d41 ilrrpar1a11&e: (I} IM ~~e of tM off-site pawu so1Uces co1UrinaillJ rltd Fefural ptrtJllO" mpply ro IM 1/umlow11. bwu on-nu. arrJ. (l) rlr.t! ~r ITOllSfn scM~s when rhe 1111nnal souru <fAC powu u Ion. Two planJ gTOupillg1 are~ il1 tJrU part fer cltu~g rlr.t! imafar:e of 1"4 pref~tl power supply to tht! safe slulldown bm: fl fl tJ1ld 13*. Tiie 1112 group u characuriud by /earures a,uqciaud wir/a flTl!alU iNUpeNkna and rethurdanq of S!'urcu. tzNI a mon1 dairalM tnuufa scl&t!IM. IJ sius ~simple. las dcsirobk uff-siu power .rysrems and swi*clryard capabililk1. TM importanet: of IN .Ji11r groupillgs bcco-s eviMn1 1111M11 comhirid with *he potemiai
/or losing off-~ por<<r tbit: IO U'!Jere and aJTenvty sevqe weallia.
3 - 10
(Page 23 of 45) P.3. f I of ~o GUIDELINES AND TECHNICAL BASES FOR NUMAR.C INlTIA11VES SL~RC87.00 THE OFF-SITE POWER SYSTEM IS IN THE 11 GROUP IF: (1) A-~* ANSWER CAN BE ASSIGNED TO CONOmON "A" BELOW, (2) A *m* CAN BE ASSIGNED TO ~IIHER CONDmONS "B(tr QB. "B(2)", BB..OW. A. AD off-site power SOUJUS ;ue connected co the unit's safe shuldown buses through (I) one swirchyml. cr (2) two er more cla:lrically camected swill:hyards. B(l) Tbe o<<mal somce of AC power is from lhc unit main genemor and there arc no aaiomatic tramfen and one or more manual rramfen of all ufo sbllldown buses lO prdmed er alimme off-sile soarces.
)
lbe normal sovcc of AC power is from the uoit ma.ia 1menuor and lhere is one 1a1romadc nnsf'er 2Dd oo mauial rr.msfen of all safe sburdowD buses bJ one preferred or ooe alEmWe otf*si!e power S011Ke. 01HER.WISE 1HE SITE IS ASSIGNED TO 1llE llL2 GROUP. Part lE: Detennille On-site AC Power Daft:n Characteristic Group (P Group) Sire nucepdbiliq to lo11 of off-siM powu is separoud izuo 1hru ba.sU; groups, baud 011 combin.a.liDns offeazurts. T~
~ featwa an: (1) ~nu ofoff-si/8 powu, (2) Jel/UC wtatlru p<Nlllial, measured dlMr by ~rioice OT recurrt11Ct ~. t11lll (3) cssr~y uvere rvmslia:. po1Ullial. TM followu.1 rablu eSllJblislr t~ off-sire power de.sign cltarocleristk group.
REVIEW TI{E INDEPl::NDENCE OF OFF-SITE POWER GROUP, SW GROUP ANµ ESW GROUP, AND ___, j A. J- 11
(Page 24 of 45) GUIDELINES AN1> TECHNICAL BASES FOR NUMARC INTI1ATIVES .'.WMARC 87-00 USE lHE FOUDWING TABLES TO DEIERMINE lHE OFF-SITE POWER DESIGN CHARACTERISTIC GROUP. ESWGllOUP s l 2 J 4 J 1 2 J 4 l
" ' Vn n n l [\. Pl Pl pJ
" l(r; s s w Pl Pl Pl z A Pl
" n I']
G J n n Pl ,, PJ G J Pl Jl a " PJ
" P.11 0
u ,, 0 u
" PJ p Pl PJ
' " Pl p PJ pJ
" " " " " " Pl
' TableJ.S. Tablel9'a
)
NOTE: Coasral pimq are susceptible liO long damioo LOOPS as a n:slllt of c:uremely severe wealher associaced with lnuricancs. As
- resuk. planes wirll otflerwi:sc sufficient EOG reliabilii:y and configur2lion and lows suSceplibility IXJ sevm: weather even~ may be in a higher coping duration ca~ solely due to die probability of a~ induced LOOP.
B. IF A PLANT 1S SUSCEPTIBLE 'IO A HURRICANE INDUCED LOOP AND HAS HURRICANE RESPONSE PROCEDURES WHICH MEET THI! GUIDELINES OF SECTION 4.2.l OF nns DOCUMENT, USE THE
. FOU.OWING TABl...ES TO DETERMINE 1HE OFF-SITE POWER DESIGN CHARACTERISTIC GROUP.
J- 12
(Page 25 of 45) GUIDELINES AND TECHNICAL BASES FOR NUMARC lNITIATIVF..S ~UMARC IJ7-00 OFF-SITE POWER DESIGN CHARACTERISTIC GROUP MATRIX For Hurricane Exposed Planl'!i a..~ (" e.. '"'
..i-- o-'
0 ~ ~ £{... OSITES
'!; y-Pr l
--*7, z J 4 '
j z ESWGKOUP pt
" In- ,,. n 1"39
(' Pi PJ s pp n ,.,. s z n ..,. w l
" w "
G ,,. ,, G n
*u
-o
> Pl Pl
",, ,, u a
0 J I'! P3 n p 4 Pl
" ,, " ,, p 4 I'! P3 J I'll n J n P3 "DDIOl1ll Sl11I Ul'GllAHAT1SISUJ1ID 10 IMrUIMllKl'4UOll0.1'LUf1' SPllCll'IC ~CA!d 5SUnlO\llN :uQllllUIMlllf' A1'ID l'llOcltllUlll: Wiiie& PllOVIH AN llMIAHCllD 1-8°"11 COJ'llllG aJ'~ UIDlla AlrlTCPATID BLmlllC&IUCONDmONS.
Table J-6b
')
3.l..2 Seep Two: C1as1i'7 Tbe £merittac1 AC Power Collllgandoa Afrcr 111.e lihliliot.>4 of losi111 off-~ polllla', 1/,. re""11daney of 1Jw ~r1ency AC ~r sysrcwt is rh.e ~:l:r mosr impont1111 c~ to Siad.on bl1Jd:a111 mi. W-ah 1naur EAC synarr ~. the po1cn1ial for stmion blackout diminisMs. a.r doc1 tlw liUliltood Df corr dama,e. T1w imporfaltU of EAC r~ u refl<<ud in this procedure rlrrou1h tire 11.1c affow tlislin&r EAC <<Hfjipradote f'Ol'PI: A Cltar~ "1 hislily rctbuulmu and indepauielll EAC sourcu ro sofe s~1dow11 tqllipmml; B Hlwilrr bma- IA4ll rypkaJ ndwulanl wul Wl4pcndDu £AC sources to safe shutdown
~
D Havits1 w lowut kYd of ituUpaulency and redJuulmu:y in EAC soJU'Ces powering safe sluddown equjpmcnl.
)
J - 13
(Page 26 of 45) PJ* !'f of uJ GUIDEI.L'lfF..S AND TECHNICAL BASE.S fOR NllMARC INI1'IA TIVF.S SUMARC B{-00 Place~nl in QM of W! groups lisll!d ~~nds 0111/tc n~T of EAC stalUilry rower supplies available tuid *~ numbu required to opu112 AC-poWt!r~ ~cay Mas remo'lal equipmelll Mcessary 10 aclrine and mailtrain safe shrudown ill a sralion bladD111. Overall, iM frt!OIU tlr6 level of EAC redunsifJn&y, 1he lu.r resrrictivl! art! 1he suuion bladco111 coping durations and maiinwM EDG failUTe rain before longer coping dwOliDns are reqllired, or carrecri111! acdon.s becotM n<<USZZry. The potellliDlfor ucl!u EAC ~r souras robe U#d tU Alur1UJ1t: AC u mrecr/y related ro 1hc aisling level of EAC redllJl/lmu:y. Silu:e EAC rl!tbuulancy is an imporuml panur2rer for tUlt!rmining stalion blackout coping duration catl!1anu, EAC powa- 10unu rt!lil:d upo11 o.r A/ll!rrraze AC power sources ""'"llOI also be considered when assessing I Accordingly, w followin1 procu1 preduda rlw UH of an EAC powu source a.s botll an inplll ra tkt~ the £.4.C group and an Altt!rnale AC saurct!. T1Us proce1s elimiluue1 IM pott!ntial for "'double cowrring* rlae valiu of C11' iNH11idwJJ EAC power SIJllTCI!, bolll as pnvtlrlili1 dw nation blad:Dul, aNl ill l"Up0fldin1 to ilS occurrence. To illiutnuc r/W point, coruida a lingt. anil SU. tlrDl Juu I/tree EAC power $Dlll'CU, and Ml!tb only one for saft! s/uaJl,qrvn. 11rU siltt can IM classijim as mlu!r a OM-<Jakl/-tlwe siu (EAC Group AJ: or a one-olll-of-rwo Jire ( EAC
-) Gro"I' CJ willl lire lllird F.AC pqwr sourctl ~ m a piOIDllial Allanat.e AC pt1WD' source, if it mftU 1~ cri1eria for AllD7UZU AC ~tl ill A.ppaldk B.
THIS STEP CONSISTS OF THREE PARTS: PMT2.A DETERMINE THE NUMBER OF EAC POWER SUPPUES NORMALLY A.VAJUJJLE: PART2.B DETERMINE THE NUMBER OF NECESSARY EAC STANDBY POWER SUPPUES; AND. PART2.C SEL£c;-T THE EAC POWER CONFIGURATION GROUP. ( J - 14
(Page 27 of 45) GUIDELINES AND TECHNICAL BASES FOR NUMARC INTTIATIVES :"tUMARC 87-00 Part l..A Determine lhe Number or EAC Power Supplies Normally A:Yailable A. SINGLE UNIT OR MULTI-UNIT SITES !fITH NORMALLY PEDICAIED POWER SUPPLIES Coum the toW number of saandby power supplies (see Appendix A) normally available ro the blacted-001 unit's $3fe shuldown equipment dun are not bcin~uscd u 311 Altanate AC power SOUJt:e. B. MULTI-UNIT SITES wrrn NQRMAU.Y SHARED POWEB sum JES Count lhe row number of dedic:ared and shared standby power supplies normally available 10 safe shutdown equipment at each sile ch.al are not *bei:nz used as an AllC:mllle AC power source. j Part 2.B Determine the Number or Necessary EAC Standby Power Supplies TM number of E:AC slllltllhy ~r Dppliu rctplind for station bladou.1 is based on w AC loads natkd al tcuh uni' ID ranowJ tkcay Jwai (int:lllding w hctU gOIBOUtl U, AC-powered tU<:ay Mal rmruval systems) in ort!Lr ro achieve and mainfain sa/t! ~ wirh off-siu f'OWN!' llNIW1ilabk._ I
' The ruimbcr ofEAC SkJNJJry J""Wr so11Tt:u n<<asary ro oprraut safe s/ua.duwlt ~ may ~ Leu than 1htu required for l.OCA loalb.
Tiu! IUllnber of 11<<asary EAC sll>>tJiby power SOIU'CU sltDllld. ~ tkrenniMd U, acco!Ullins for IM individual safe slwulOwn. loads, or illferrcdfrom rlu! n~*s dui1r1 basis for opoazillg ClaR JE AC 1tquipnun1 withowt off-site AC ptl'WO'. B. MJ1l.'D-t!NII SITE.S WIJll NORMAILY SHABB> POWEB. SUPP'JFS Counl die ll>C:il nmbet of EAC SQlldby power s*pplies necessary ID operile safe shutdown eqaipmem ~ uliMioebbclou:fuc alllllli11ad1uilr- ~~Uew' ~ ~ l C)~S. o-f- o-fHr--fe fdLl1an
. perafrca.+o.. -JF-Frti-'f- 03
] - 1.5
(Page 28 of 45) GL1DELINES AND TECHNICAL BASES FOR NUMAJlC INn'IATIVES Part 2.C Select lbe EAC Power Coafiguratioa Group
.n.~{)~
,,, v"- ~,..,
USE THE TABLE PROVIDED BELOW TO SELECT THE EAC GROUP: < ~ l{ _,
~,e J ff\"'
Table J..7 ""'
---SH-AllE-D EAC GROUP AN----D SUPPLIES NECESSARY FOR SAFE SHtrrDOWN D____.EDIC...............
ATED-----,) SUPPLIES AVAILABLE
- A I 3DEDlCATED A 1 4 B 2 .5 B 2 4 c 2DEDlCATED c '.JSHARED D 3 4 D 3 .5 D l 3 D I 2SHARED Dedka_. - ror EA.C staadbJ ~ 111ppUa DOit *orm.U1 slllll'~ wida olber u111t1 .
al* MW Shared - for EAC atudbJ powu Sllpplla ha. wllld1 - aambsr an 11ormally capmllle vi P"-..-tdhll AC power to sat* sln11dowa ciq.. pmnt at 1111ore *llao. one anit ** a s1..* 00-11 utlf. - p 12. .-- ~ r ret:fa ..J FA I{ - '-t - O -:3.
- U UJ' vi lbe ICAC ,-er - r a s an norma!IJ sbred mmoq 11aJ.. at a multt-111111 site. lb.. Is die lulal aamber ol allarelll and chdkalild 110Grce1 ror ~ oalll al lbe J.2.J Slep Tllree: Determine Tbe Calcal*ted EDG RelllibiUtJ TM rudr EDGrclillbUity u wed ill conj~dDn wit.II IN! siu':soff-siu powudttsign characterisaa (i..e .* Pl, P2, or PJ}.
and w £AC cOlf/lflllYld.o4 (A. B. C. ar DJ ro alDmiM tlw unit's requiral stalian blad:o111 copinr dwalion. T~ wiir EDG reliabillq is caklllated /);, tnllUdgUtl tJw iNlividuaJ £DG reUabilily far tlw /aJt 20, SO, 01td JOO danands for e~lt m111:hiM. How611U, if IM 10ral nMlll6a' tfvalUl dorttutib u kss 1Nul 100 (t!.g .* newly Ucensed plmu, EDGs wlaich ha.~*e unbrgotU Urlelllitle mainunance or a reliabiIUy rt!qualijicazion provamJ, 1he EDG reliDbilirJ uver IM Ian 20. tJnd 11te Ian 50 if availabh. can ~ averaged and compared 10 the evallllllio11 criuri.a ill Seclion J.2.4. If 1he unit'J' EDG reliability over 1he Ian 20 dl!mands is:> 0.90, or:> 0.94 over rite lasr SO donanlU. then IM !Ulir may sekcl tJn EOG 1arge1 rdiabilirj of dJJiQo 0..95 or 0975 a.J arailai in Section 3.2.4.
)
- 3. 16
(Page 29 of 45} GUIDELINES AMO TECHNICAL BASES FOR SUMA.RC INrrIATIVES N'UMARC 87.00 TM objective of I~ rltree-IUr tzpproad to reliability ~asuremelll is ID prowu grearu depth of undusUJIUiing regarding reliabiliry rrends. TM 20-dernand sample st!r is IM most volatile, and offers a very st!nsilive indicarion of EDG performanct!. SiMe rJtis UulictJJor move.s willi eai:J1incrDN!Nalfailure111' Sll&CUS, ii u nm consUkred a refiabk-asure of long-rerm pafo""411U. Similarly. the IO<J..tUmtJNl sample ut offu:t a lo11g-1erm rreNI indicarion, while providillg lindred iluiglat 10 recen1 rreNJ.s dlle r.o dlUa .rmoolhilr.& effects. Tise 50-demm&d sampl.e se1 bridges rise rwo indir.a1ors while also prtTViding an inumwditut: lewl. Ta!m roge1hn-, Ilse se1 of iNJUa1ors provides a fairly t:D"'Plete picture of EDG reliabilily. -\-0. ~
<'!)... V.-' 0
(?f' v\- DETERMINE THE CURRENT UNIT EOG REI JABII.IJY: pe"..J ~ if (I) CALCULA'IE U£E MOST RE.CENT EIXi REl..IABll.ITY FOR fMJi.EDG BASED ON TIIE LAST 20, SO, AND 100 DEMANDS (USING NSAC-10 DEFINmONS
. e----_,,..
AND MEillOOOLOGY CONTAINED IN SEcnON F TIIAT DOCUMENT OR EQUIV Al.ENI). CALCULATE.THE NUOJ:AR UNIT AVERAGE EDO REI..IABIUTY FOR THE
"*I LAST 20 DEMANDS BY AVER.AGING TIIE RESULTS FR.OM (1), ABOVE.
I CALa.Jl.AlE lllE NUCl.EAll UNIT AVERAGB ED0 REl...IA.Bll.ITY FOR TIIE UST SO DEMANDS BY AVERAGING lHE RESULTS FR.OM (1). ABOVE. CALCULATE TIIE NUa...E.All UNIT AVERAGE EOG RELIABll.lTY FOR THE LAST 100 DEMANDS BY AVERAGINO lllE RESULTS FROM (1), ABOVE. J.2.4 Sl~p Four: Determine AUowed EDG T*r1et RellabiUtJ Tire Mininumi EDG reliability lltollllJ N tarrt:ud t11 0.95 per~ pu EDG for planu in EAC Grolll'J A, B. C. oNi 0.975 per demaluJ pq F.DG for plalus ill EAC Group D. Tlwtr re6abiliry levels s1tould be considered miniMUM U1Tge1 rel.iabilidu Ea.ell p"'1lz s1totdd UIJJblisla 1.111 EOG Reliabillly Prorram tU 01111iMd in Appendix. D 10 1/Us docwneflt. Plana wlricll sal<<I a rarg.n EDG reliabilitJ o{O.!J75 sltoald llliliu rl!U 1argc1lnclin1/wir reliability program. If i~ diuel genD'OIDr ~11 /alb below IM 111r1111 reliabilily ltrv.I sp<<ifkd. action Jliould be Ulk11 1hrousli an EDG rt!liabilil] program sucli. a.r 11!1 forth ill AppatdU D ro resrore IM 111rp1 rrliabiliry levft. TM iuti1 EDG reliabilil] f()f" llte Ian 20. 50, and JOO demoNb colculaud in rite pmMW siq pravidu w allowed targei refiabilfry wed in tk~rmininl mininwm required Stoiion bltJdo111 coping dwtuions in r~ ner1 su:p.
) - 17
(Page 30 of 45) Gl.'IDELINES AND TECHNICAL BASES FOR NUMARC INrnATIVES ~UMARC 87..00 AU.OWED TARGET REllABILITIES ARE DETERMJNED AS FOLLOWS: {I) COMPARE THE CALCULATED AVERAGE NUCLEAR UNlT EDG REUABIUlY DE1BMINFD IN SECTION 3.2.J TO nIE OUTERlA BELOW: Eyaluarlm Crir;ria LAST 20 DEMANDS > 0.90 REI.IABlUTY I.AST SO DEMANDS :> 0.94 REUABllJTY UST 100 DEMANDS > 0.95 REUABll.JTY ('2) IF TIIE EAC GROUP JS A. B, OR C, AN.12. ANY OF THE THREE EVALUATION CRITERIA IN SECTION 3.2.4, SlEP FOUR. PART (1) A.RE MET, THEN TIIE NUCLEAR UNIT MAY SELECT AN EOO RELIABfLITY TARGET OF .EJ'DiER 0.95 OR 0.915 FOR DETERMINING 1HE REQUIRED STATION BU.CKOlIT COPJNG DURATION. IF UIE E.AC GROUP IS D, AND ANY OF 11IE THREE EVALUATION CJU1'ERIA IN SECTION 3.2.4, srEP FOUR. PART (1) ARE MET, TIIEN TIIE All.OWED EOG RELIABll.ITY TARGET IS 0.975.
)
(3) IF THE EAC GROUP IS A, 8, OR C, AND NONE OF THE TIIR.EE EVALUATION CRITERIA IN.SECllON J.2.4, STEP FOUR, PART (I} AR.E MET, lHEN 0.9, SHOULD BE USED AS TIIE RELIABILITY TARGET FOR D:STERMINING THE REQUIRED STATION BLACKOUT COPING 0 DURATION. ADDmONAU.Y, IP 1lIE RELIABIUIY IS LESS TIIAN 0.90 BASED ON TifE UST 20 DEMANDS. 'nlEN ACCE'I'ABIUJY OF THE COPING DURATION RF.SUI.TING FROM USING 0.9!1 MAY REQUIRE FUR1HER JUSTIFlCATION. IP THE EAC GROUP IS D AND NONE OF 11IE THREE EV ALUATIO?" ClUlERIA IN PART (l) ARE MET. nm REQUIRED COPING DURATION' CATEGORY CALCULATED IN STEP FIVE. SECTION J.2.5 SHOULD BE INCREASED TO THE NEXT HlGHEST LEVEL (I.E., FOUR HOURS BECOMES EIGHT HOURS; EIGHT HOURS BECOMES 16 HOURS). 1- 18
(Page 31 of 45) G UIDELL"iES AND TECHNICAL BASE.5 FOR :stJMARC INITIATIVES NU:\fARC87-00 J. 2. S Step Five: Determine Copiag Dunlioa Cate1ory USE 1HE TABLE PROVIDED BELOW TO DETERMINE TIIE COPING DURATION REQUIREMENT IN HOURS: Tablel-8 ALLOWED EOG REQUIRED OFFSITE POWER EAC GROUP TARGET REUABILlTY COPlNG DURATION' GROUP {Fr..* Sectloa J.l.2) (Per D11*aod) CATEGORY
~Jirem Sec*loa ]..2.1) (Fro* Seclloq 3.l.4)
Pl A 0.950 2 Pl B 0.930 4 Pl c 0.9.SO 4 Pl D 0.975 4 P2 A 0.950 4 PZ B O.!lSO 4 W' -7 P2 c 0.97, 4 P2 c 0.9SO B Pl* c 0.950 4 P2 D 0.915 *a ne D 0.97$ 4
)
Pl A 0.975 4 Pl A 0.930 B PJ* A G.950 4 Pl B 0.915 4 P3 B USO 8 Pl* B 0.950 4 Pl c 0.915 I PJ* c 0.97$ Pl c O.!ISO ' 16 Pl* c o.uo I PJ D 0.975 I PJ* D 0.97.5 4
- Denotes site apll'ade adriltalahle to impleme.tatio* ol plant spec:lnc pre-hunlcane .sbu1down reqoireme*ts llDd proced*res wlllch pro*ide a* enhanced copint capability 11.nder au1icipat~d burricaae cu..Utiou.
J .1. IS Reqalred Acdo11 S~p Fiw (S<<dott 3.2.S} ~oft. of 1118 /011r c:opiltr tbuatio11 c~iol'U1 diml.ssed. U. tM NRC Stazion Blac/t:QUI Regulazory Guidi l.JSS: IWO "°"1'1,fow hours. dglll lrour1, or 16-ltoun. PIDnu ill rhc d1hl and 16-liour caugoril!s shDllld ruukrr4lu! acrioru ro r~e rir.t consis~111 wiJlt NUMARC SlllliOtl Blad:o111 /niriati11c 1. THE FOLWWING COURSES OF ACilON ARE AV All.ABLE TO REDUCE THE ASSESSED RISK OF J - 19
(Page 32 of 45) GlilDELINES AND TECHNICAL BASES FOR NtJMARC INnlATlVES NlJMARC 87.00 I STATION BLACKOUT: (1) IMPLEMENT ACTION 10 REDUCE TIIE REQUIRED COPING DURATION TO AT llAST 1HE FOUR HOUR CATEGORY BY: (a.) REVIEWING PI.ANT-5PEOFIC WEATIIER DATA; (b) MODIFYlNG mE SWITCHYARD TO OIANOE raE 1-0ROUP; AND/OR, (c) MODIFYlNO TIIE.PLANTTO OIANGE TilE EDG CONFIGURATION; AND/OR. (d) IMPROVING EDG RELIABll.ITY. (2) INSTAIL OR UTlUZE AN EXISTING ALTERNA1E AC POWER SOURCE TIIAT MEETS lHE CRITERIA PROVIDED IN APPENDIX B. 3- 20
(Page 33 of 45) ca. (( t ( 00
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(Page 38 of 45) A-t-tuc:li D I
~ Francis W Ettel To: John F Ankney/FirslEnergy@FirslEnergy iiltiii' 03/31/2003 09:09 AM cc: Kevin J Lynch/FirslEnergy@FirslEnergy, Sum T Leung/FirslEnergy@FirslEn ergy
Subject:
Re: Loss of offsite power frequencygi John, The grid related loss of offsite power frequency is 3.16E-021yr(or1 in 31.6 yrs) al Unit 1 and 2.31 E-02/ yr (or 1 in 43.3 yrs) al Unit 2. These are lhe plant specific values based on operating years and actual occurrences (1 in 15.8 yrs for Unit 1. 0 in 9.93 yrs al 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-Site Power at U.S. Nuclear Power Plants - Through 1999q, July 2000. Bill John F Ankney John F Ankney To: Francis W Etzel/FirstEnergy@FirstEnergy, Sum T 03/30/2003 09:32 PM LeungfFirstEnergy@FirstEnergy cc: Kevin J Lynch/FirstEnergy@FirslEnergy
Subject:
Loss of offsite power frequency Gentleman, 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 slated 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 date. I am presently on the back shifl for 1R15. Thank you, John __ j
(Page 39 of 45) Douglas L McBride To: John F AnkneyfFirstEnergy@FirstEnergy cc: 03/31/2003 07:28 AM
Subject:
Re: Diesel Generator Reliability[] As per lhe Station Blackout program, I keep a database of EDG start demands, load demands, starl failures and load failures. Per the SBO program we are required to keep above 97.5%. Obviously, we respond lo any failure and make "prevent recurrence~ corrective actions if they occur. As or 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 EOG could not have ran with no river waler. The second is when the 4 kv bus undervoltage relay locked up and prevented the EDG from loading during the LOOP/SI test Again, not an EOG failure, but it could not have loaded. As of Loday, 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 lo review it and it is on my shelf above my desk. OLM John F Ankney John F Ankney To: Douglas l McBride/FirslEnergy@FirstEnergy cc: Kevin J lynchlFirstEnergy@FirstEnergy 03/3112003 01 :37 AM
Subject:
Diesel Generalor Reliability Doug, I am presently perforrning a calculation where I need to know the reliability of the safety Diesel generators. Unit 1 UFSAR gi11es 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 the limes the DGs do not start when tested? Is there special maintenance done to assure reliability? Could you please respond to the above questions byWednesday4-2-03 so that I can answer a CA? Thanks, John
(Page 40 of 45)
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BEAVER VALLEY POWER STATION* UNIT 2 I 'DUQUESNE LIGHT COMPANY J.O. 12241
.El)
I r- a SUPERSEDES S l!i W FILE NO. (El) (25*341 FU~~US.'4.::.LLJ.'~.:Ju....L.L.L.m--..1.-....L..J. .c.L..--L-:....J..:~ N
-,:~_.,;;-,:::,,.:<: _: . :-*"*1I REMA" KS ILIMITTO 22 CHAR,..CTERS If< BLANKS)
!CODES OR Sl'ECIAL REOUIREMENTSI
!53-74) A M
! e
' DATE TO REVIEWER (Ell iI I
2
- 2. ~GS MFR'S DOC. NO. (El) (LIMIT TO 24CHARACTERSll< BLAr.IKS)f:1'7-l!OI fllllCl..UOE oac. REV.OR OATEI o3 /~o REVIEW STATUS (Al 1-----~--....;.;;~.:::.:.:..;;..;.;c..:..:....:~"""----r-----i i
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. :* 1 MFWS NAME (El) (LIMIT TO 2DCHAFl"CTERS If< BLANl(SI (61-601 APPROVED AS REVISED IN SPECIFICATION
. - -*- . i COL. T INJ>UST'RIES ATE MON' I DAY 1 Rl2lhllll DOC 1311 MA)( OAYS 132..:131 ECO I l TVPE lA IN REVIEW CCI
- 0 8 I '3 0 I .., ' (Ell /"\ (Ell 1 FUNCTIONAL TITLE (Ell ILIMITTO 137-801
['44 CHARACTERS & BLANKS)
'300 SIA~! l'E..ST "RE"PO'RT VOL. I - 5' D
~ ~~C£!.~~:=L.!...L::.J.=.J>...!..-L..:....L.m--.L....L--1,..c.L..~'.,../;T.l SEQUENCE NO. ICI QW'.8 0 0 3 l 8 ooo9 REVIEWER COMMENTS:
I LI" I *
. -:/
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(Page 41 of 45) i I PAGll* ENGINEEBING REPORT SRE£T 1 or 5 no. Fairbanks Moni* FILE Engine DIYl1lon N1JMllEB ll-206l47C DIESEL GENERATOR SET FOR l>llTE 7-20-78 Ii BtJIRCI' BEAVER VALLEY POWER STATION UNIT 62 I
-.:-*, :; -=.*=-..._:'* *-...'::-.' ~*;*11
- BEPOBT 300 START AND LOAD Tlrl.B ACCEPTANCE QUALIFICATION
. . I I INTRODUCTION ll
*..... *.* :i' A 300 Start and Load Acceptance Qualification Test was run on the second I; diesel generator unit S/N206147B for Beaver Valley Nuclear Power Station #2
*: --.','*, _-** . ;.- 1 as required by Stone and Webster Purchase Order 2BV-230.
Colt Engineering Instruction 11872825 Rev. 3 which was approved by Stone and Webster details the method of test and acceptance criteria. A total of 300 Start and Load Acceptance runs were required; 270 from wann standby temperatures and 30 from nonnal equilibrium temperatures, with no more than three failures allowed. RESULTS A total of 272 valid Start and load Acceptance runs were made from warm standby
- temperatures with only one failure to meet the acceptance criteria.
A total of 30 valid Start and Load Acceptance runs were made from normal operatina equilibr1um temperatures with no failures to meet the acceptance criteria. Additional runs were made which are discounted. That is, they are not considered valid runs nor fai1ures, for reasons such as operator errors within the parameters defined in the test procedure. I I The results of the Post Trial Inspection (per Paragraph IX of 11872825, Rev. 3) is covered in the material 1n Appendix P. I CONCLUSION
--1 The diesel generator unit successfully passed the 300 Start and load Acceptance Qualification Test.
I i ATIAGHMENTS Appendix A - Approved copy of Colt Engineering Instruction 11872825 .Rev, 3 - 300 Start and Load Acceptance Qualification *
..***-1*
I Appendix B - Test Logs 43, 44, 45, 46 (with Attachment A), 46A (Sheets 1 &2),
! 47, 48, 49, 50 and 54 whfch record perfonnance data and contain notations, where applicable, to events happening during a run, or maintenance performed.
(Page 42 of 45) (.a (c. { 0 o~c -DEC- 0 ?..'-16 f<;c v I 0 ft1 to ch. G- r.!JI / oT ( RTU A.1.0020 Calculation Affected Document Review Checklist Calculation: I 0 ~O - DEC - 0 2. '{6 Revision:
- - Addendum: N Ill YES NO DOCUMENT/SECTION Do the Calculation Assumptions and/or Conclusions affect:
- 1. TheUFSAR? 0 .on
- 2. Technical Specifications? D ~
- 3. Design Basis Documents? D ~
- 4. The Operating Manual?* D }ti.
- 5. The Abnonnal Operating Procedures?* D ~
- 6. Emergency Procedures?* D :Kl.
- 7. OST/BVT Procedures?* 0 .H{
- 8. The ISl/IST Program?* D )C1
- 9. Other Plant Procedures?* D Js;a:
- 10. Equipment Setpoints?* D ~
- 11. Other BVPS Calculations? 0 fi!..
- 12. Vendor Calculations? 0 )?J, 13 Other Vfls?* D lil.
- 14. Equipment Specifications? 0 )it.
- 15. Procurement Specifications? 0 ~
- 16. The Fire Protection Safe Shutdown Report? 0 Sit.
- 17. The EQ Program? D ~
- 18. Any other Design Basis documents? D )'l
- 19. Any radiological inputs and/or D ~
consequences? a 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
(Page 43 of 45) Page 1 of 1 DESIGN VERIFICATION RECORD NOP-CC-2001-01 Rev. 00
~~&~~JM:trf§~.!P~. *~~* . . ~~- '"*-~j~'i!~7~i~&~
DOCUMENT(S)/ACTIVllY TO BE VERIFIED: Ccdc- too~~-OE:G-Ol.'f~ R~v.o Co '"' Porra.+101.t it>\!' ..sto.t~&'i.. BCQ.ci<Gu.l. 0 SAFElY RELATED 0 NONSAFETY RELATED SUPPORTINGIREFERENCE DOCUMENTS c.R oz. -o 1 ct DESIGN ORIGINATOR: (Print and Sign Name John F* A"'~~~t
~Ciifil!lifiPAiw~~~ea~-
- VERIFICATION METHOD {Check one)
DESIGN REVIEW (Complete Design 0 ALTERNATE CALCULATION 0 QUALIFICATION TESTING Revfew Checklist or Galculation Re'dew ChBcklisl) JUSTIFICATION FOR SUPERVISOR PERFORMING VERIFICATION: NIA APPROVAL: (Print and Sign Name} DATE rJ flt N.!ft COMMENTS, ERRORS OR DEFICIENCIES IDENTIFIED? DYES NO RESOLUTION: (For Alternate caJcufation or Qualification Testing only) N.!Pr RESOLVED BY: (Ptinl and Sign Name) DATE N./Pr DATE
'1/81/03 DATE 4-/q /o~
Cale. 10080-DEC-0246 Rev. 0 Attach. H Page 2 of 3 Page 1ol2 0 CALCULATION NO. ArstEneJ@' CALCULATION REVIEW CHECKLIST 10080*DEC*0246 "' REV.O NOP-CC-2001 *04 Rev. 00 - UNIT2 QUESTION NA Yes No COMMENTS RESOLUTION REFERENCES ,/ 1 Does the slated obiectivefpurpose clearly describe why the calculation is being performed?
- 2. Are applicable codes, standards, design/licensing basis documents, etc.. including edlHon and ,/
addenda v.trere appropriate clearly ldentrned?
- 3. Do the references reftect the appropriate revision? ,/
INPUTS ,/
- 4. Are design inpuls clearly identified and lheir source documents referenced, including revision level as aoorooriate?
5, Are lhe design inputs relevant, current, consistent with design/licensing bases and directly ./ applicable lo the purpose of the calculation, Including appropriate tolerances and rangesfmodes of operation? 6, Are all design inputs retrievable? If not, have they been added as allachmenls? ./
- 7. Are preliminary or conceptual Inputs clearly Identified for later confirmation as open assumptions? ./
AsSUMPTIONS ./
- 6. Have the assumotlons necessarv to oerform the analvsls been adeaualelv documented?
- 9. -> Is suitable Jusllficallon provided for all assumptlons (except those based upon recognized ./
en!llneerino craclice, chvs1cal constants or elementarv sclenllflc cnncioles)?
- 10. Are all assumptions for the calculation reasonable aoo consistent with design/licensing bases? ./
11, Have all open assumptions needing later confirmation been clearly identified on lhe Calculation ./ cover sheet, includinc when the open assumpuon needs to be closed?
- 12. Has a Condition Report been issued for open assumplions if required? ./
- 13. Have engineering judgments been used? ,/
- 14. Are engineering judgments reasonable and adequately documenled? ,/
METHOD OF ANALYSIS ,/
- 15. Is the melhod used appropriate considering the purpose and tvpe of calculation?
- 16. Is the melhod in accordance wilh applicable codes, standards, and designflicensing bases? ./
IDENTIFICATION OF COMPUTER CODES [Ref: NOP-SS-1001) ,,/
- 17. Have the versions of the compuler codes employed in the design analysis been certilied for this aoolication?
- 18. Are codes property Identified along with source, inputs and outputs? ./
- 19. Is the code suitable for the analysis being performed? ./
- 20. Does the computer model, thal has been crealed, adequately reHect actual (or to be modified) ./
clanl condiUons (e.a .. dimensional accuracv, tvce of model/code oclions used, time steos, elc.l?
- 21. Is the computer output reasonable when compared to Inputs and what was expecled? ./
COMPUTATIONS ./
- 22. Are lhe equations used consistenl with recognized engineenng practice and des1gn/l1censing bases?
- 23. Is justification provided for any equations nol in common use? ,/
- 24. Is the justification reasonable?
- 25. Have adjustment factors, uncertainties. empirical correlations. etc., used in the analysis been ./
correc~v applied? C
- 26. Is lhe result presented with proper units and lolerance? ,/
- 27. Has proper consideration been given to results lhal may be over1y sensitive to very small ./
changes In Input?
I Cale. 10080-DEC-0246 Rev. 0 Attach. H Page 3 of 3 I Page 2 of 2 FlrstEn~ CALCULATION NO. CALCULATION REVIEW CHECKLIST 10080-DEC-0246 REV. 0 NOP-CC-2001-04 Rev. 00 UNIT 2 QUESTION NA Yes No COMMENTS RESOLUTION CONCLUSIONS
- 28. Is the magnitude of the resull reasonable wtien comoared lo inouls?
- 29. Is the direction of trends reasonable?
- 30. Are slated conclusions just1f1able based on the calculation results?
31, Are al\ pages sequentially numbered and marked 'lllllh a valid calculation number? 32. 33, Is arl information legible and reproducible? Have all changes in the documentation been initialed (or signed) and dated by the author of the ct\amie and all reti1.1l1e0 re\f\ewers? 34, Have all calculation results stayed within ex1stlng design/licensing basis parameters?
- 35. If the response lo Question 34 is NO, has Licensing been nctiried as appropriate? (i.e. UFSAR or 36.
Tech Spec Change Recuest has been lniliatedl. Does \he calculation meet Its purpose/objective?
- 37. Has lhe calculation vendor used ;ill applicable design information/requirements provided?
- 38. Did the calculation vendor determine if lhe c:alculalion was referenced in design basis documenls and/or databases?
- 39. Did the Preparer determine If the calculation was used as a reference m the UFSAR?
- 40. If lhe calculalion 1s used as a reference m the UFSAR. is a change to lhe UFSAR required or an updale lo lhe UFSAR Valida\lon Database, ii app\lcable, reouired?
41, If the answer to Question 40 Is YES. have the appropriale documents been initialed? 42, Is the calculat1on acceptable For use? ,/
- 43. Whal checking method was used to re111ew the calculation'? Check all lhal apply.
- spot check for math
- complete check for malh
- comparison with tests
- check by alternate method
- comparison wilh previous calculat1on Review Summary:
ee $1.A-rt.s a..'r""ee ~~ f. J..{ 30"-33 Iii Technical Review I I Owner's Acceptance Review (Required for calculations orepared tiv a vendorJ Paul Dearborn pJ R""'ewer (Prin/ and S;gn Name~ W
- Date
~! s/c5 Reviewer: (Print and Sign Name)
/'lift-Approver: (Print and Sign Name)
Date N. I fl. Date Nt A- rJ I Pr}}