ML19207C247
| ML19207C247 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/14/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-08-02, TASK-RR NUDOCS 7909100547 | |
| Download: ML19207C247 (12) | |
Text
TseA p a nucoq j%,
UNITED STATES s.
g NUCLEAR REGULATORY COMMISSION y
L I WASHINGTON, D. C. 20555 8
o August 14, 1979 Docket No.
50-155 Mr. David Bixel Nuclear Licensing Administrator Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201
Dear Mr. Bixel:
RE: TOPIC VIII ONSITE EMERGENCY POWER SYSTEMS-DIESEL GENERATORS is a draft evaluation of Systematic Evaluation Program Topic VIII-2, Onsite Emergency Power Systems - Diesel Genarators for Big Rock Point.
We have not found. adequate basis in our review to conclude that the 7
single diesel generator (D-G) at Big Rock Point has adequate capacity to perform its safety function if required for a loss of offsite power coincident with an accident. Therefore, we request you perfom a review to determine if the D-G has the required capability. As a minimum, you should provide the information requested in Enclosure 2, including a description of analysis perfomed, test data, results and conclusions.
If the results of your review do not demonstrate that the D-G can supply the plant safety loads in their current configuration, Enclosure 2 requests that the proposed corrective actions be provided in your response.
We request that you provide the information discussed in Enclosure 2 on a schedule that will allow resolution of this matter before the present outage is completed.
Sincerely, o-W Y%
/
s Dennis L. Ziemann,'
ief Operating Reactors Branch #2 Division of Operating Reactors
Enclosures:
1.
SEP Technical Evaluation -
Diesel Generator, Big Rock Point, dated May 1979 2.
Request for Additional Infomation
,.g.g" cc w/ enclosures:
See next page 79001 00697
Mr. David Bixel August 14, 1979 CC Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Hunton & Williams George C. Freeman, Jr., Esquire P. O. Box 1535 Richmond, Virginia 23212 Peter W. Steketee, Esquire 505 Peoples Building Grand Rapids, Michigan 49503 Charlevoix Public Library 107 Clinton Street Charlevoix, Michigan 49720 K M C Inc.
ATTN: Mr. Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.
Suite 1050 Washington, D. C.
20006 f
m-
ENCLOSURE 1 SEP TECPNICAL E'!ALUATION DIESIL GENERATOR SIG ROCK POINT Consumers Power Company Occket No. 50-155 May 1979 E. W. Roberts
..* d <G :, th. tn --
3 o
CDNTENTE 1.0 INTRCCUCTICN.
1
- 2. 0 CRITERIA...........................
2 2.1 Diesel-Generator Loading
?
2.2 Bypass of Protective Trips 2
- 3. 0 v!SCUSSICN AND E'/ALUATION 3
3.1 Diesel-Generator Loading 3
3.2 Bypass of Protective Trips 4
a.0
SUMMARY
5 c.0 REFERENCES..........................
6
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SEP TECHNICAL EVALUATION BIG ROCK POINT oo DIESEL GENERATCR 3,
Docket No. 'C-1 5
-)(ab_:3 ss 1.0 INTRCOUCTION The ob,iective of the review is to determine if. the onsite AC gen-erator for the Big Rock Point Nuclear Station has sufficient capacity and capability to supoly the required automatic safety loads during anticipated occurrences and/or in the event of postulated accidents af ter loss of offsite power.
The requirement that the onsite electric pcwer supplies have capacity and capability to complete the required safety functions is contained in Generai Design Criterien 17.
General Design Criterien III, " Design Control," of Appendix 3, "Cuality Assurance Criteria fer Nuclear Pcwer Plant and Fuel Repreces-sing Plant," to 10 CFR Part 50 includes a recuirement that measures be provided fer verifying er checking the adequacy of design by design i
rev ews, by the use of alternate or sicolified calcu13tional methods, by the perfcrmance of a suitable testing program.
er Regulatcry Guides, IEEE Standards, and Branch Technical Pcsitions ahich crovide a basis acceptable to the NRC staff fcr c0moliance with G:CI7 and GCCIII include: Regulatory G;ide 1.9, "Selecticn of Diesel Garc ater Set Capacity for Standby Pcwe-Supplied;" Regulatory 3a e '.103, "Derindic Testinc nf Diesci Generators Used as Onsite 3.=r Systems at Nuclear Ocwer Pl?nts": IEEE Stancard 387-1977, "Fri-
- = 'a 'cr Jiesel-3erar2tc-Units Applie is Standby Power Supolies for d
'Aclear ?cwer S tatic s ;" ETP ICSB?. "D" 'se'-Gereratcr Reli3bility
";21 ifi cation Testirc": ard BTP ICSB17. "3 esal Generiter Protective T-io Circuit 3ypassas."
Snecif'cally, tnis review will eva'uate t~e loading of the diesel-
- ere-ite 3rc bypasses of cratective trics duri ng accident ceaditions.
' e SEP ev ews ':r Tcci es ::I-1. :11-23 anc I
- I-5. A wil ' eva ';a t e "a
i
-' =s e '- c en e-3 t cr -,'
ty cualica';nn.
The aer odic tes*'nc of i
?
(s*jft'An*.A
.),.o t f r-e s'. ~
the diesel-generator will be evaluated as part of SEP Topic VIII-!. A, "Petenti al Equipment Failures Associater with Degraded Grid Voltage."
?.0 CEITERIA 2.1 Diesel-Generator Leadina.
Reculatcry Guide 1.9, " Selection of Diesel-Generator Set Capacity for St,'ndby Pcwer Supplies," provides the basis acceptable to the NRC staff fcr ioadirg diesel-generator t.r ts.
The follcwing criteria is used n this report to determine i
ccmoliance with current licensing reouiraments:
(1) The autcmatically-connected loads on each diesel-generator unit should not exceed the 2CCO-hour er 90% of 30-minute ratino.
(Leads must be conserv-atively estimated utilizing the rameplate ratings of -'otors and transforners wich motcr efficiencies of N% or less. When avail ab'e, 3ctua l measured loads can be used.)
2.2 Sveass nf Prete :tive Trips.
' ranch Technical Posi ticn /371 I:5317, "Diesal-Gene-atcr Protectiv9 7'4p Tircuit 3ypasses," specifies that-fl)
I're desian cf standby diesel lenerater systems D
D should -etain only the engine overspeed and the QO gene ater di#ferenti 31 trips,nd bypass all othe O 3 i g,_
tri25 under an acci dent condicn W h b
2 (21
!f ctber t-ics, in addition t ' t' e engine overspeed 2nd generatcr diff erential, retai ned f cr acci-w dent Cond# tiCrs, an 3CCeptab' 3 teSi gn shoul d prC-vi de two or mor= independent measurements of each cf tnese trio parameters.
T 'p ' cgic s houl d be s uch t hat liesei-generatcr tr io wculd reouire speci-
- i C cc'"C'rer*. ' ogi c, 7
9. ~ 1, -v g>*
.),,) ' f 4 e '
mo 3.0 DISCUSSION AND EVALUATION D
D
<> av 3.1 Diesel-Generater Loadica.
Mhi f
a
-Q Discussion.
!n the Commissien "emorandum and Order, dated May 26,1976 (Reference 1), Big Rock Pc'nt (BRP) was granted a lifetime exempt'en frem the single-failure recuirements of 10 rRF Part 50 f].46 and A;cendix K, Paragraph I.D.1 as apol ed to e LOCA caused by a break in a ccre spray lire and a concurrent ngle f ailure in the remaining core spray system.
- ncluded in the orrer was a plant-life exemotien frem the recuirenent that the ECCS shor*-term and long-term cooling functions be invulnerable to a single f ai'ure which disables onsite pcwer assuming off site pcwer is not ava " able.
This was alicaed in viow of the unusually high availability of o#fsite power at Big Rock Pc'et, together with imcroved reliabili y nf the ensite diesel and guaranteed availability of a backup dierel f or long-term cooling.
The 0' rector's ccmments rote that, in view of the small sice of this plant ccmpared with the system capacity, trics of the plant due to internal causes are relatively unlikely to causa a less of offsite power.
Censevuent to the above action, 3i q Rcck Poi nt has only one ensite diesel ge,e-ater.
On January 19, '.979, CPto providec a current list of loads con-rec *.ed to tne sing'e diesel gene-ator-Supp'iad motcr control cent'r 10 0 rec;i ed ander the fo:1 7si ng corditiens (Re#arerce l'. ; 'a) less cf c##: te r:wer uitbcut concurrent loss c' Cre' ant acci1ent (LOCA'
'ad, t
'cs s of c'#si te e r.<e r cniccicent #
3 LCCA.
During escn o' -"e c ::rdi ti :rs, rpcc 3.;ac i : c f * -a n amm. na f hcl ratina af each
- nter, meis ;ee d curren t
r each icaf. 3rr ' a:
calcu ated K'!A for each l
' Cad.
The calcul ated K '.'A ' c 3 0 i r g C c n s i ' 71
- ivalV repres en's t he dC* U d
a-s
- "a diesel :en e-it er f "ce it tilices tho easurec cur ent i
'a n
f e * + -' ' ' c ; t"e va'oes.
Therefcre. it 's not recess ary t3 use the 907.
9# # i c' enc V *o de*ernice etcr. ads.
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There is no autcmatic shedding of ' cads on the diesel generator-supalied saf ety bus ( ?31 upon loss of c" site pcuer.
Therefore, when the dit ;el generator tie breaker is clcred, the gercratcr must sapply all leads demanded at that time, inclur ng matcr starting currents.
The Big Rock Point Technical Speci#ications require a load test of the diesel generatcr te 120-200 KW gene-ater cutput for 20 minutes between each reacter ccerating cycle.
Ev a lu a t ien.
The maximum loading of the dipsel generatcr occurs when there is a loss of offsite power with a LOCA.
The total autanatically-connected load as shown cn the licensee's load tabulation is :76.75 KVA.
The electrical generater f 0G) ?000-hour rating (Refer-ence 3) is 200 KW at 0.3 P.F. cr 250 v,V A.
The alectrical generator
.'0G' has no 30-mi nute ce short time ratirg ' Reference 14).
The con-nectsd Icad is 26.75 KVA l11%) above tha 2000-nour rating.
Theretcre, since *bere is no automatic iced shedd qq and sucsecuent secuential ica
- rq af t he diesel rjeneratCr: the di !sel oener3tcr must be capable cf accep:i ng a step 1:cd if 11% over th' 2:00 bour ratino plus the
- a-ting leads of mc+crs.
- 2. 2 S o tss c'
-otective Trios f
04scussien.
'"e Commission's."emorandum and Order, dated
."ay ?5. 1975 directed CPfc to:
"cci'y the emergency diese' gene-!!:r and diesel-driven i
9 9l 0
9
- i ra w a' er pu~p protective tri;:s
> bypass the cratec-ob
- ive t#i::s durir; 3cci dent condit"Ons except fcr reten p ig n I}
\\ I tier c' t"e engire overspeed anrf gener3tcr diff erential (b]gb LD
- ,r ent trics, unless additional 'v:: ass 'rios are 90-0 Oved by the Cirector, Nuc' ear R !!ctor Regulation."
31s ad On 3' E:C33 l', CPCC nce'f iec the e~cegeacy diese'-cereratcr t 4: :"-:;4t y 11 r+n n '"cse trics
- seci ?ted e.ith icw %be
l C r ? ; '. / S, " ' ;" 20 c i "
- C 41:c' te~cer]t
' and corFr?':r Overcur ent, a
n.,f.wf5 521h !
- 4 ' "
utilizing two independent senscrs and coincident logic, while main-taining the engine overspeed trip as crf ginally designed.
No modifi-catiens were ircorporated for the diesel-driven fire water pump, since t'e cnly p3rameter that will cause a trip is engire overspeed.
Evaluation.
The NRC staff review of the Big Rock Point diesel generater prctective trip circui-bypasses was completed in the SEQ fer A: endment No.15 to Facility Op? rating License No. CPR-6, dated Oc *c h er 17,1977 (Rv rence 2).
The following statement was included e
en rage 2? cf the SER:
" Based on our review, the modifica:icns to the emergency diesel generatcr are acceptable because they (a) satisfy the criteria cf BTP EICSB 17, (b) significantly enhance the reliability of the ensite powe-system, and (c) ccm-aly uith Secticn (31 (iii) of the emorandum and Order, dated May 26, 1976."
During accident conditions the diesel generator engine overspeed electrical t-ip is retained as origninally designed.
All cther diesel generatcr protective trips utilize two sensors and coincident logic.
7"e efore, the use of protective trips 'cr the Big Rock Point diesel gene ater is in agreenent with BTP EIC5H7 and complies with current licensing raouirements.
D PfD bU
.U "';RY 7
l WJlJ_SJ 1 b,h
~~e tycass :f M es e' generat :r crM ec*.'ve trips is in compliance W*-
c a r-a r.t 'i censi ng c-i t eri en.
TM - e v en cf cualificati:n mc i
testi ; c' t%
- esel cenerater will 9 cc oieted with SEP T:pi:s III a-c.'!!!-:.A. -espectivel:
As s:ned 'n t'e ^^Ca sutmit 31, s me of the 1 cats en t' e Scsel gene *2' " 1re 'ntermi!!3nt, and simul
- 3eeom accurrence *f all '03c5 is a'
- a l '/.
Wen e W", :"P Miesel go erst?" MY "nt be C3 CAD'e Sf s40-4 3'j --
7 reg g- ' *s4 q, ring icc4 a
7prqi;4 ggg; gjgcg,
%rg ig
-r.
.c}G G:- (O
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no sequential loading of the supplied safety bus; the connected load on the bus exceeds the d'esel generater 2Cr0-nour rating: and the surveil-l ance tests do not verify the diesel generatcr's capability to supply the emergency loading.
Therefere, it it requested that the licensee perf om detailed review to determine the capability of the diesel gener3tcr to supply the connected leads during a LCCA, with loss of cffsite power.
Dm D
JwoJ
5.0 REFERENCES
p' Ib O Y A
1.
'demorandum ana Creer, by the Cccm';sicners, C in Ehe di:
o CPCo, Big Rock Poi rt, dated May 26. '.976, cage 9.
2.
Letter NRC (D. K. Davis' to CPCc (D. Bivel', dated Octcber 17, 1977, attached reccrt. page 11, "E'fety Evaluatica by the Office of Nuclear Reacter Regulaticn Sucrorting i limited ECCS Exempti cn f or the 197S Operating Cycle."
3.
Letter CPCo hi. S. Sewell) to MRC ' S. J. ChilkT dated Febru-ary 27,1976, page 29, attached rcoort, " Report on Evaluaticn of Adequacy of Emergency Core Ccolino System."
Letter CPCo (D. A. Sixel) to NRC ( J. L. Ziemanni dated 'inu-ary 19,1979, " Additicnal Infccmat icn Regarcing SEP Topics V!-7.3,
'! :I - 1. A, ind '!I:-2."
3ene a' Jes'cn :ri terien 17. "E'ecc c Dewer Systen," of Apoen-i 1ix A, "Gere-C Design Cri teria f Nuc'aar Pcwer 31 ants," to
'l CFR Part 50, "Ormestic L'cenri", n :'rnructi :n 3ad Util izat' cr e
3c il i ti es."
5.
3aner d Desi gn : te-i:n :':, "D a. ;r :'rtrn',
faccerdix 3,
"'u!'ity Ass ur ance :-i t eri a f or 1.: lese P%er lants inc Fuel 2e:':ces? ng o' 3-t s, ' :: " O C.iF P !rt cr, ' Ceres t i : L icens ng af i
S-y _tisa sac _-:'i:3t en 73c4
- c; i
0 p ;,.,. s.,
. n.-<. i r.o
7
" Standard Criteria for Class IE Pe,.er Systems and Nuclear Power Generating Stations", IEEE Std. KP,1974, paragraph 5.2.4 8.
" Criteria for Diesel-Generator Units Aoplied as Standby Power Supplies for Nuclear Pcwer Stations," IEEE Std. 287, 1977.
9.
" Selection of Diesel Generator Set Capacity for Standby Power Supp' i es", Regu ' atery Gui de 1. 9.
10.
" Periodic Testing of Diese' Genercters Used as Onsite Power Systems at Nuclear Plants," Regulatory Guide 1.108.
11.
" Diesel-Generator Reliability Qualification Testing," BTP ICS32.
12.
" Diesel-Generater Prctective Trip ^ircuit 3ypasses," BTP ICSB17.
12.
Big Rock Point
- Technical Specifications," pages 11-17, paragrach 11.4.5.3.
7 0
D sL M
- (0j Jk 3 3 is I
(L ; ; \\
- w e't
. s os., t a e
ENCLOSURE 2 REQUEST FOR ADDITIONAL INFORMATION BIG ROCK POINT 1.
What is the maximum possible diesel generator (D-G) loading with loss-of-affsite power during accident conditions? Provide a detailed analysis to support your findings.
2.
What is the maximum step load which the D-G must assume?
3.
Provide a description and the results of test (s) and supporting analysis used as the bases to demonstrate the capability of the D-G to accept the step load (s) (maintaining the voltage and frequency within accept-able limits) and supply the connected loads for the required time during accident conditions.
If additional testing is required, it should be in conformance to the applicable sections of IEEE Std. 387-1977 and Regulatory Guide 1.9.
4 Provide a description and the results of an analysis to determine if the duration of the degraded voltage and/or frequency will impair the performance of the safety related systems and components supplied by the D-G if the results of the test (s) identified in Question 3 indicate that the voltage and frequancy are not within the limits recommended in IEEE Std. 387-1977 and Regulatory Guide 1.9 during the step loading.
5.
If the information requested above does not demonstrar,e that the diesel generator has adequate capacity for a loss of offsite pcwer coincident with an accident, describe the corrective action you intend to take.
.N ',T/[3