ML20034E331
| ML20034E331 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/22/1993 |
| From: | Thayer J YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYR-93-005, BYR-93-5, NUDOCS 9302250312 | |
| Download: ML20034E331 (2) | |
Text
n YANKEEATOMICELECTRICCOMPANY
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580 Main Street, Bolton, Massachusetts 01740-1398 February 22, 1993 BYR 93-005 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Mr. Morton Fairtile Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support
Reference:
(a)
License No. DPR-3 (Docket No. 50-29)
(b)
NRC Inspection Report 50-029/90-18
Subject:
UPGRADING OF TIE CABLES
Dear Mr. Fairtile:
In reference (b), NRC notes that Yankee Atomic Electric Company (YAEC) committed to upgrading the tie cables between the non-class 1E 480 V station service buses and the Class 1E 480 V buses at the' Yankee Nuclear Power Station (YNPS) during the next refueling outage.
YAEC has re-evaluated this commitment in light of the permanently defueled condition and possession-only status of YNPS and has concluded that the subject cables do not need to. be replaced.
The basis for YAEC's original commitment, which is noted' in Inspection Report 50-029/90-18 (Attachment),
was that the possibility to overload the tie cables existed 1) during a design basis loss-of-cooling-accident (LOCA). event and 2) during the performance of emergency diesel generater monthly surveillance I
testing. However, such a possibility no longer exists at YNPS.
I Because the reactor vessel is permanently defueled, and the l
Possession Only License prohibits power operations and transfer of-fuel into the containment, a design basis LOCA event can no longer occur.
Furthermore, the current required to power the spent fuel 1 pool cooling equipment or to conduct surveillance testing on the emergency diesel generators are within the existing tie cable calculated ampacity.
Therefore, YAEC does not intend to replace-the subject tie cables.
9302250312 930222 PDR ADOCK 05000029 G
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l United States Nuclear Regulatory Commission Document Control Desk i
Page 2 P
If you should have any questions concerning the above information, please notify Jane Grant or me at 508-779-6711.
Sincerely, YANKEE ATOMIC ELECTRIC COMPAhT V
ay ~K.
Thayer Vice President and Manager of Operations Attachment l
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R. Dudley, NRC, NRC NRC Region I NRC Resident Inspector t
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Attachment 4
m U.S. NUCLEAR RESULATORY COMMISSION REGION !
Re; ort No. 50-0?9/90-18 0:caet No.50-029 License t,0.
D;R 3 ar6ee Atomic Electric Company Licensee-v Fac ility Na*re : Yankee Rcwe Nuclea,Po.wer St.ation E liar. Pt and Ro.e,,MA
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Ins:ertic, Concu:.ted: Scote e er 24-2E, 1993 ke)kIhi M lE ' M d D I-ste: tors:
R. Mainew, Reactor Engineer, Plant Systems date
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>W fo fo y
J.~V La ra. Re a c t o r E n g i nee r, Plant Systems cate Sect
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EE. CRS
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/O - 7 4 4c R. Enat'ia, Rea:ter Engireer, Plant Systems
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_t L. r.ay. Reacto-Engineer, Plant Systems cate Se:: ion, EE, C' A::covec by:
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[. J. An #rson, Chief Plant Systems Section, date Eagineering Branch, DRS I
9 Inspecticn Sur-ary: lesretticn Report No. 50-029/90-IS
- eas Inspe:ted: A special arrcunced team inspection to review tre emergency
..esel geae ate-re:lacemeet c: ification and testing program.
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' e s,, i t s : 1) 0 e violation regarding inadecuate testing was'icentified during
- e re. e. :'
- e I te see's tes: pr gram anc
- si results. Ini s viciaticn is j
O's:wsse:
f* 5e: :- 4.2
- 2) Tre lite see's cualification tests cem:estrate:
E;3.
- 6.4:
j to carry tre cesign bases loads. The E;5 test : c; ram
.e cic net cemenstrate ibe performance cf the EDS units at 0.8 rated :c.e-factcr.
'nts iss e is als: ciscusse: in Section 4.2.
90/IND253 2jp.
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11 Calculation YRC-553 ceronstrated that these new poner cables can withstard the continu:us current rating of the new EDGs. However, curing tre EDS sncrt time capabilities (600 kW for 2 hrs), the cables will te overicaced by S.4 *.. Based upon the guidance provided in.
IEEE 242-1975, "Re:ommended Practice For Protection and Coordination cf Indastrial and Cor9e-: al Pc er Systems", the lice'nsee concluded
'tnat this sh:rt time overleading condition was acceptable since the cable te pe-ature will reach ap?r:ximately 102' C which is below the 130' C a perature allowed by IEEE-232 during emergency everloading.
Frese t', there are ro sueveillante recuirements to test the EDGs at 600 La ciner inan tre original qualification tests. The current TS
~
-e: vires the Itceasee to test the ED3s at 200 kW for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on a '
e:etnly irte.a' a-: 4 00 b a' eve y 15 c:nths for one hour. IEEE 242 allcws e ergea:y 1:a:ir; cf the E03 for 100 hcurs per year. The tea :: : 'u:e: that t*e EC3 : ables are acequate to support the un'is' re-f -ra :e.
450 V ite Cat es t
The non-Class lE 453 V staticn service buses provide power to the Class lE 450 V buses in ou;n associated tie cables. These cables are class'f e: as ncn-uclear safety-related. The rated ampacities of teete ca:Ies 's ace uate ta su: ort normal plant ooeration with enrecte: cac;e tem: era.ures cf 60* C.
However, these cables are estette: to ca ry ap;re trately 135.6 *. of the rated current capacity cur:n; cesice cases events (LOCA). This Condition is espected to be 130 ca> s te sa: crt ECCS eculpment operation following a prese t fer tOCa. Caiculatice Y~C-536 ciconstratec that under this overload c:rcitica. the tie ca:!es' temperature rise could reach approximately 115" C.
Ine licensee cas c:r:luded that these cables can operate at this nig e-temperature f c appro Imately 1.7 years without degradation.
The licensee has coerittee to upgrace the tie cables during the next refueling cutage.
Curing this ins:e: tic. ine team also selected safety-related motor cre-ate: valves to verify proper cable si:ing to support equipment cperacility.
No cefi:1e cies =ere icentif:ec.
4.4.3 ECG r.el 011 C:nsu stic, The tea? reviewed the fuel oil consumption calculation YRC-858 and ass:: tate: cre-atir; procedures to cetermine the solu e cf fuel re:.* e: 1: s :::rt c:e-atic-cf the EDO at rated capacity and at cest;- tasis loading cendition.
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Attachment 6
n U.S. NUCLEAR REGULATORY CCMM:5510N REGION 1 Re; ort No. 53-029/90-18 02:=et No.
50-0?9 License No. 0;R-3 Licensee-lar6ee Atomic Electric Cpypany Facility NaTe: Yankee Rowe N.clea Power Station E
- ste: tion 4:
Erltor, MA anc Rowe, PA ins:e: tion Conducted: Secte-ter 24-28, 1993 keh k IM.u W
/E ' 2-4 ~9 C)
Inspectors:
- 4. Maines, Reatter Engineer, Plant Systems date Section. EB.,0Rt g
W fo fo y
UT E Lara, Reactor Engineer, Plant Systems date Section, EB. CRS 7
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.. -f,gqQ R Enatia, nea:ter Engsreer, Plant Systems date
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Section EE, CRS b
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L. c.ay, Eeacto-Engireer, flant Systems date Section, EE, D^
A;;rovec by:
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/* Yb C. J. Ancf rson, Chief Plant Systems Section, date Eagineering Branch. DRS
,lry ection Summary: Insfecticn Report No. 50-029/90-16 freas Inspected: A special arrcunced team inspection to review tre er.ergency
- esel gene
- ate-re: lace.eet r:ci f ica: > u.. c.
+ esting prograrn.
- es i s
- 1) 0 e.iciation regarding inadecuate testing was icentified during t
t*e re, e- :' t*e >':e see's test pr gram ard t st ressits. Inis viclation is
=
rs: sse: i' le:t :- 4.2 I) Tre liceesee's cualificaticn tests Ce-Cesteatac
- E15. ceia:. i to :arry the cesign bases loads. The EDS test :-ogra-f cem rttrate the performance cf the ED3 units at 0.8 rated cae* faticr.
ci: nct IN5 155 e is als: cis:Usse: in Section 4.2.
90/IND253 ]$
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11 Calculatten >RC-S53 cer.:nstrated that these new power cables can withstand tre continu:us current rating of the new EDGs. However, curing tre EDS sncrt time capabilities (600 kW for 2 hrs), the cables will be over cacec by S.4 %.
Based upon the guidance provided in.
IEEE 242-1975, "~eco= ended Practice For Protection and Coordination cf Industria; a.d termer: al Pc.er Systems", the licensee concluded that inis sher: time overl:ading condition was acceptable since the cable te ;e ature will reach approximately 102" C which is belew the 130' C tempera:ure allo ed by 1EEE-242 during emergency everloading.
Prese-:1, there are to su veillan:e recuirements to test the EDGs at I
600 t. etrer inan tre e-iginal cualification tests. The current TS 1
~
re: vires the liceasee to test toe ED3s at 200 kV for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on a
?:r.: sly irte.a' a-: 4 00 6 a' eve y IS m:nths for o.e hour.
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alle.s eterge-:y 1:actr; c' the EOS f or 103 heurs per year. The te a ::-:i:ed ima: tre E'S : ables are ace ;uate to support the
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450 V Tie Cat'es
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The ncn-Class IE 430 V staticn service buses provide power to the Class IE 450 V buses th ou;n associatec tie cables. These cables are class f e: as nen-utlear safety related. The rated ampacities of
- ete caries 's ace:. ate ta succort normal plant operation with enrecte: cao;e te.: era;ures cf 60' C.
However, these cables are es:ec e: to ca-ry ap;reateately 135.6 % of the ratec current capacity
- urte; cestgr cases events (LOCA). This condition is expected to be trese-fer 130 caw s to suppcrt EC"5 eculpment operation following a LOCA
!aitulatice Y~C-33' c(monstratec that under this overload c :i:10, the tie ca:!es' temperature rise could reach approximately 235' C.
lae licensee ras cer:luded that these cables can operate at this higae-temperature f:- appros tmately 1.7 years without degradation.
The licensee has co-titec to c; grade the tie cables during the next refueling cutage.
Curtn; this ins:ectica, the team also selected safety-related motor cpe atec valves to verify prcper cable sizing to support eculpment 0;eratility.
No cefi:1e*cies were icentifiec.
4.4.3 E00 Fuel 011 C:nsu o: ion The tea reviewed the fuel oil consumption calculation YRC-858 and asse::4:e: c;e-atir; pr :ecures to cetermine the so'u e cf f t el re:.'-e: :: 5.:::rt c;e-atic-cf the EDO at ratec :a;a:ity and at s
cesig- 04s15 loactng c ndition.
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Attachment 4
U.S. NUCLEAR GEGULATORY CCMMIS$10N REGIO *l 1 Re; ort Na. E0 02_990-18 i
- mhet No.50-029 1:ense No. DTE-3 1:ensee-bar6ee Atot1C Electric Company Tatility NaTe: Yankee Rowe Nuclea-Power Station
!*!:e:11on It E ltor., MA and Ro.e, MA Ins:e:ti:n Concutted: Secterter 24-22, 1990 IC ' 4 d O key k ThW Ins:e: tors:
cate
_R. Matnea Reactor Engineer, Plant Systems
,EB.,DRp Setti m
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W fo fo p.
z J. V Lara, Rea: tor Engineer, Plant Systems cate Section. EB. CRS k). %1d_'
/0 - Z 4 40 date R. Etatia, Reatter Engtreer. Plant Systems 5ection, EB, DRS b
bdm L (A <dt2 __ t iC -2 4-9 e cate L. r.av. Reactor Engineer, flant Systems M
5e: tion. EB, C'
/* Yb 4; roved by:
W ^M C. J. Ancerson, Chief, Plant Systems Section, date Ergineering Eranch, DRS Ins;ectice Sum 9ary.
Insrettien Report No. 50-029/90-18
[ eas Ins ectep: A special aercunced tea-inspection to review tre emergency
- esel generate-re:laterect r::tfication and testing program.
- e s.,1 t s
- 1) 0*e viciatice regarding inadecuate testir; was icentified during 1*e ee. e. :' ;*e 1*:erste's test pregram and t.st results.
Tn'<
tica is
- 5;.sse:
1-
"e:t :- 4.2 I) Tre liteesee's salificatien tests cem:esteate:
E;33 : ;a: > :, to carry the design bases loads. The E;3 test :-og-am fa: tor.
.e cer:ntirate the performance cf the ED3 units at 0.E ratec :cwer 01: net Inis iss e 's ais: Ofstusse: in Section 4.2.
'/O/ incas 3 2,.
4 3)
Calculatten YRC-559 cenanstrated that these new power cables can withstand tre continu:vs current rating of the new E9Gs. However; caring tre EDS short time capabilities (600 kW for 2 hrs), the cables will be overleaced by S.4 *.. Based upon the guidance provided in,
IEEE 242-1975, ";e:ommended Practice For Protection and Ccerdinati:n,
~
cf Industrial and Carme-:"al Po er Systems", the licensee concluded
'that this short time overicading condition was acceptable since the cable tet e-ature *ill reach approxicately 102' C which is belew the 130' C ter;erature allo.ed by IEEE-242 during emergency everloading.
Erese-t'y there are no sueveillance recuirements to test the EDGs at 600 L. ctrer inan tne original qualification tests. The current TS
' ~
re:Oires the itceasee to test the ED3s at 200 kW for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on a'
'~
c:ntnly trie.a' a-: 4 00 La' eve y 15 m nths for e.e h:ur. IEEE 242 allcws eter;e-:y 1:a: r; c tne E ; for 103 heurs per year. The e
tea ::-::c:e: inat tre E:3 : ables are acequate to support the un'ts' pe-fr-ra :e es 4
450 V Tie Cat t The non-Class IE 453 V staticn service buses provide power to the Class l'E 450 V buses throu;h associated tie cables. Tnese cables are class *f e: as ncn-u: lear safety-related. The rated ampacities of 1"ese co les $ 5 ace:cate ta support nereal plant operation with enrecte: caole tem:eratures of 60* C.
However, these cables are e=recte: to carry apcre.1rately 135.6 ?. of the rated current capacity cur r; cesige bases events (LOCA). This condition is expected to be crese-: fer 133 da>s to sa: pert ECCS eculpment operation following a LOCa. ~41culatten Y;;-335 cemonstratec that under this overload c:e:itte. the tie ca:!es' temperature rise could reach approximately 115* C.
ine licensee cas cer:luced that these cables can operate at this hig*e* temperature f: approximately 1.7 years without degradation.
The licensee ha s ccemittec to upgrade the tie cables during the next refueling cutage.
Curing this inscettien the team also selected safety-related motor coe-atec walses to verify proper cable sizing to su: port ecuipment Operability.
No deficie-cies were tcentified.
4.4.3 605 F el Oil C-nsu stic, The tear reviewed the fuel oil consumption calculation YRC-858 and ass :: ate: cre-atir; procedures to ceterr.ine ta+ vo'ure cf fuel re:.' e: 1:
- 5. ::rt c;e-atice cf the EDS at rated capacity and at cesig- 0a515 leading cendition.
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