IR 05000266/1996303

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Exam Repts 50-266/96-303OL & 50-301/96-303OL

ML20198F818
Person / Time
Site:	Point Beach
Issue date:	08/07/1997
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Patulski S WISCONSIN ELECTRIC POWER CO.
References
50-266-96-303OL, 50-301-96-303OL, NUDOCS 9708130150
Download: ML20198F818 (2)

Text

e - 9 August 7, 1997 Mr. S. Site Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, WI 54241 SUB. LECT: NOTICE OF VIOLATION (NRC INSPECTION REPORTS 50 206/96303(OL);

50 301/96303(OL))

Dear Mr. Patulski:

This will acknowledge receipt of your letter dated June 30,1997, in response to our letter dated January 23,1997, transmitting a Notice of Violation associated with a plant procedure that aligned the Vital DC Electrical System. We have reviewed your corrective actions and have no further questions et this time. These corrective actions may be examined during future inspections.

,

Sincerely, original signed by J. H. Jacobson John A. Grobe, Acting Director Division of Reactor Safety Docket Nos. 50 266; 50 301 Licenses No. DPR 24; DPR 27 Enclosure: Ltr dtd 6/30/97 S. A. Patuiski Point Beach to USNRC See At'. ached Distribution DOCUMENT NAME: G:DRS\P0108 7.DRS To receive a copy of this document]ndicate in the box: "C" = Copy without /

attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE Rlli M Rill Ay Rlli %Q) d Rlli A _y l NAME JLennartz:Jpyh MLeach Q\M^ -JMcCorfnick B JGrotie i7 jffv DATE 08/cg/97 !/ 080 /91)L/ 08/6/97 08/7 /07] V ~

~qQ)d 0FFICIAL RECOMD COPY

'

9708130150 970007 ll!!!!,!{!!!kk , .

ADOCK 05000266

,

PDR V PDR m

. .

S. Aunust 7. 1997 cc w/o encl: R. R. Grigg, President and Chief Operating Officer, WEPCo A. J. Cayla, Plant Manager cc w/ encl: Virgil Kanebic Chief, Boiler Section Cheryl L. Parrino, Chairman, Wisconsin Public Service Commission State Liaison Officer Distribution:

Docket File w/ encl Alli PRR w/ encl Alli Enf. Coordinator w/ encl PUBLIC lE 01 w/ encl SRI, Pt. Beach w/enci .TSS w/enci OC/LFDCB w/ encl- LPM, NRR w/enci CAA1 w/enci

' DRP w/enci _ A. B. Beach, Rill w/enci - DOCDESK w/ encl DRS w/ence J. L. Caldwell, Rlli w/enci

' '

. -

$y

. .

'

,RA.%$7 TUE 10:45 ~ 'PBNPHP FAX N0, 414 755 8200 P.02 Wisconson Electnc POWER COMMNY 2h W W mo.som 20% w.oAeeM $32o12046 e

NPL 97 0356 10 CFR 50.4

,

June 30,1997

,

Document Control Desk U.S. NUCLEAR REGL*L A a ORY COMMISSION Mail Station PI-137 Washington, DC 20$$$

li '

Gentlemen: .

DOCKETS 50 2fd AND 50 301 TECIINICA_L SPECIFICAT10N B ASES CHANGE AUXILIARY ELECTRICAL SYSTEhd r.ullH, tit &UH NUUL EAK PLAN i. tJNL i S t ANU 2 By letter dated January 23,1997, the NRC forwr rded NRC Inspection Report Nos. 50- .,

260/96303(OL) and 50-}01/96303(OL). Enclosed was a Notloo of Violation related to a plant procedure that aligned the Vital DC Electrical System to a configuration for which it was not

) designed. We lasued a reply to the Notice of Violation in our letter NFL 97-00>0 catea rebmary l 24,1997. In our reply, we committed to revise the abnormal operating procedure AOP 0.0 to ensure that a battery charger does not power a DC bus without a battery connected to the bus.

, . Based on the performance limits of the PBNP battery chargers, the connection of a battery is necessary to buffer the DC output sufficicatly to ensure the quality of DC power. In our reply, we committed to clarify the Bases of Technical Specification 15.3.7 to ensure that the aforementioned battery charger performance limits are explicitly stated. We originally committed to complete this change by May 1,1997.

In our letter NPL-97 0210 dated Apnl 30,1991, we requested an extension to complete the commitment by June 30,1997. The NRC accepted this extension in a letter dated May 15,1997.

We have completed this commitment today.

We have evaluated the aforementioned TS Bases changes pursuant to 10 CFR 50.59 and determined that the changes do not constitute a change to the specifications,'nor do they introduce an unreviewed safety question. Therefore, NRC approval of these particular changes is not required. -

ffEC'D PBNP JUL 021997 m g uu m,* o,, ,c e s,4 ,

]Ill *

WGCMW 5f10

_

~ .,

'

7;.

JUi.-29-97

., ,~

ftE'.10 45 ? W PBNP HP

- -

.3

,r FAXN0,4147558260 P.03 Document Control Desk June 30,1997 Page 2

~

The modined page to the Techalcal Speel8 cations is provided as an anachment to this letter.

)

, Please contact us if there are any questions.

.

Sincetely,

'

"

o S/ n- $-

' ' Douglas F. Johnson Manager Regulatory Services i

t.nd Licensing ,,,

ODA/kmc ,

Attachment

'

cc: NRC ResidentInspector s NRC Regional Administrator

/

, (

'

/ (

,

. ... i m ., -

3tl!.,-70-i,I TUEl10140PBNPHP '

'

f* FAX 110, 414 755 0200 P.04 transfonners. In such cases, bus independence may be relaxed under the conditions specified la the I.CO.

Patended use of safeguards bus tie breakers is allowed under speelned, controlled conditions. Per examp when a unit is fully defueled, safeguents and safe shutdown systems and equipment dedicated to that unit are

'

not required. However, spent fuel pool coo!!ng must be maintained. By limiting the loads supp!!cd by the

cross. connected huses, the potential for loss of a diesel generator due to overloading caused by the failure of a tin.bre.aker to open is minimized. Operability of shared safegmrds systemuur.h as auxillary feedwater and

,

service water must be maintained as required by their applicable 1.COs.

l l

The bus tie-breaker speelfications have provisions that the required redundant decay heat removal for the shutdewa mit wd tii, mplied ,(dundarit shared engineered safety features ter the other unit aro oporablo.

The speci0 cation that applies only to the defueled condition does not have the provision for the required redundant decay heat rertM's! fer the shudovm unit. It he pmvision for verifying the adequacy of a single train of spent fuct pool cooling in lieu of the consideration of decay heat removal for a reactor in cold shutdown.

The Point Beach DC electrical systeriihas be4n modined so that each of the four rrsin DC distribution buses, which are shared between the two units, has its own power supp!!es consisting of a safety related station banery (DOS, D06, DIOS, D106) and a battery charger. In addition to these bus-specific power supplies, a swing safety-related battery (D305) is installed which is capable of being connected to any one of the four

'

main DC distribution busesjSwing battery chargers are also provided. Under normal circumstances, one battery and one battery charger are cortnected in each main DC distribution bus. The battery charger normally shall be in service on each battery so that the batteries will always be at fb!! charge in anticipation of a loss-of.AC power incident. However, one of the four connected battery chargers may be inoperable for up to two hours to allow the transfer to a standby battery charger or return the inoperable battery charger to service.

The 7. hour outage time is based on Regn!ntnry Onidt: 191 and refinnta a rtennable timg tg assess plant status and either connect an operable baucry charger to the affected bus or prepare to effect an orderly and safe shutdown of the operating unit (s). Under unusual circumstances, two of the five safety-related batteries may bo out of servico fu A IIWted period of timo provided one of the two out of cervice batterles is retumed in r,nrvinn within the time periods stvvi6cd in Spnnifinntion l'i 'l 7 H.I.I. F.xpll;it to Specification 153.7.B.I.! is the requirement that the four connected battery chargers remain operable. Implicit to the operability of a battery charger is the quality ofits output power. Power quality can only be assured when each charger is connected to a battery that adequately filtcrs the output of the charger. A battery charger is (noperable ifits output is not connected to a battery. 'Ihe connected battery need not meet Technical Specification operability requirements. These limiting conditions for operation ensure that adequate DC power will always be available for starting the emergency generators and other emergency uses.

15.3.7 6 Bases Change f.nttnr darnd Jime 30,1997