ML20012F835

From kanterella
Jump to navigation Jump to search
Discusses 911115 Request for Temporary Waiver of Compliance from TS 3.8.1.1 Requirements.Relief Request Granted on 911114 Contingent Upon Compensatory Measures Listed
ML20012F835
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 11/19/1991
From: Zwolinski J
Office of Nuclear Reactor Regulation
To: Kovach T
COMMONWEALTH EDISON CO.
References
NUDOCS 9112040237
Download: ML20012F835 (4)


Text

.,-

7 NkL7 Y ^-

3 a ncu

/'

'g UNITED STATES 1

.., j' j NUCLEAR REGULATORY COMMISSION

'""*i#, t W ASHINGTON. C. C. 20555 a

E November 19, 1991 i

\\..v j

..+

Docket Nos. STN 50-454, STN 50-455 STN 50-456, STN 50-457 l

Mr. Thomas J. Kovach 1

Nuclear Licensing Manager Co monwealth Edison Company-Suite 300 OPUS West III 1400 OPUS Place Downers Grove, Illinois 60515

! tar Mr. Kovach:

We have reviewed your letter of November 15, 1991, requesting a Temporary Waiver of Compliance (TWOC) for Braidwood, Unit 1, and Byron, Units 1 and 2, from Technical Specification (TS) 3.8.1.1, Action statement e., and for Braidwood, Unit 2, from the TS Action statement 3.8.1.2 requirements to depressurize and vent the Reactor Coolant System.

Braidwood, Unit 1, and Byron, Units 1 and 2, were in Mode 1 and Braidwood, Unit 2, was in Mode 5.

The TS requires two emergency diesel generators (EDGs) be operable while in Modes 1 through 4 ar one EDG operable while in Modes 5 and 6.

The TSs require that when in Mot while two EDGs are inoperable, one EDG is to oe made operable within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. When in MODE 5 with less than one EDG operable, immediately i

suspend all operations involving core alterations, positive reactivity changes, j

movement of irradiated fuel, or crane operation with loads ever the spent fuel 4

i pool, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System

)

through at least a 2 square inch vent. Also, when in Mode 5 with the reactor coolant loops not filled, immediately initiate corrective action to restore at J

least one EDG as soon as possible.

4 The basis for your request was that on Thursday, November 14, 1991, at 3:05 p.m. for Byron, Units 1 and 2, and at 3:10 p.m. for Braidwood, Units 1 and 2, the EDGs were declared inoperable. Following the EDSFI at the LaSalle Station, Commonwealth Edison Company (CECO) addressed the surveillance requirements for i

a bus undervoltage condition for several feeder and crosstie circuit breakers at Byron and Braidwood. Technical Specification Surveillance Requirement 4.8.1.1.2.f.4a requires verifying deenergization of the ESF busses and load J

4 shedding from the ESF busses.

It was discoveret.; hat these breakers were l

never tested for an undervoltage condition and that no test documentation or j

test procedures existed. The affected circuit breakers are the normal or alternate Station Auxiliary Transformer (SAT) feed breakers and the ESF to non-ESF crosstie breakers.

You requested 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from 3:00 p.m. on November 14, 1991, before any of the units would be required to comply with the applicable TS requirements. This i

4

  • M @ Q+ $w b

9112040237 911119 Mi%

UtA @umyptto hf PDR ADDCK 05000454 P

PDR dh3

-M

Mr. Thomas J. Kovach November 19. 1991 request was to avoid (1) increased pressures on plant staff to complete the surveillance which could have led to errors resulting in an abnormal occurrence, and (2) a transient condition involving potential plant upsets that would require demand for the system when the system is removet' from service for testing. This waiver would also avoid an unnecessary thermal cycle on Byron, Units 1 and 2, and Braidwood, Unit 1, should you be able to prove the EDGs operable within that time period. The TWOC was granted at 6:45 p.m. (CST) on November 14, 1991, to commence at 3:00 p.m. or November 14,1991, for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

If the problem with the breakers had not been correded and at least one EDG had not successfully passed its operational surveillance test, actions would have been taken to shut down Byron, Units 1 and 2, and Braidwood, Unit 1, in a timely manner. Compliance with TS 3.8.1.2 would have been established for Braidwood, Unit 2.

I understand that during the effective period of time that the TWOC was in effect, Braidwood and Byron Stations took the following compensatory measures to ensure that the units were maintained in a safe and stable condition:

- No electrical distribution equipment, either normal, standby or reserve, would be unnecessarily taken out of service on any unit.

No switchyard activities which could perturb the offsite power sources would be allowed.

- No Fire Protection activities which could result in a transformer deluge actuation would be scheduled.

The Load Dispatcher was notified to maximize the availability of the offsite power lines servicing Braidwood/ Byron.

The Shift Management would review all surveillances and out-of-services for impact prior to authorizing the initiation of the activity.

Byron, Units 1 and 2, and Braidwood, Unit 1, would be removed from EGC for the duration of this waiver.

Division OAD would be notified to refrain from work activities in the switchyards for the duration of this waiv e

- All operating personnel would be notified via Daily Order to:

a)

Ensure these measures remain in effect for the duration of this waiver.

b)

Trip the SAT feed breaker should an undervoltage condition occur without the diesel generator breaker closing.

c)

Not perform any unnecessary surveillances which utilize the ESF and non-ESF crosstie breakers.

r.,

Mr. Thomas J. Kovach November 19, 1991 We agree that the diesel generator train's undervoltage interlocks F*suld be included in the Byron /Braidwood stations' surveillance program and will be performed on an 18-month frequency.

I granted the requested re. lief with Region III concurrence at 6:45 p.m. (CST) on November 14, 1991, based on a thorough discussion with the CECO management team for Byron and Braidwood, Region III, and the NRR staf f, to commence on November 14, 1991, at 3:00 p.m. and continue for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. This approval was contingent on the compensatory measures described above. The Temporary Waiver of Compliance was terminat ed at Byron, Units 1 and 2, at 1:28 p.m. (CST) and at Braidwood, Units 1 and 2, at 5:45 p.m. (CST) on November 15, 1991, when one EDG of each unit was declared operable.

Sincerely, Odgina1 Signed By:

John A. Zwolinski, Assistant Director for Region III Reactors Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION Docket tile NRC & Local PDRs PDIII-2 r/f PDIll-2 gray TMurley GPA/PA FMiraglia CGrimes JPartlow OC/LFMB ABDavis, Rlll JLieberman, OE BBoger EGreenman, RIII JZwolinski BClayton, RIII RPulsifer OGC CMoore ACRS (10)

GHill (8)

EJordan Wanda Jones Eleeds

/

LkP 11-2 PM/PDI D/PD[l'h 4 ADR /DRPW RIli1)/.PD if

}1_

f RBar dt JZwolinski EGre nmartd,, M lt LNoore RPulsi

rc
  1. ^#

i/0/91

// /g /91 o/JT/91 g/g)/91

/.//f/91 r>'

/

r DOCUMENT NAME:

BRAIDWOOD TWOC 11/91

Wx s

I i

Mr. Thomas J. Kovach I

Comonwealth Edison Company Byron /Braidwood Power Stations CC*

Mr. William P. Poirier U. S. Nuclear Regulatory Comission l

Westinghouse Electric Corporation Byron / Resident Inspectors Office Energy Systems Business Unit 4448 North German Church Road i

Post Office Box 355, Bay 236 West Byron, Illinois 61010 l

Pittsburgh, Pennsylvania 15230 Ms. Lorraine Creek Joseph Gallo, Esq.

Rt. 1, Box 182 Hopkins and Sutter Manteno, Illinois 60950 888 16th Street, N.W., Suite 700 Washington, D.C.

20006 Mrs. Phillip B. Johnson 1907 Stratford Lane Regional Administrator Rockford, Illinois 61107 U. S. NRC, Region III 799 Roosevelt Road, Bldg. #4 Douglass Cassel, Esq.

Glen Ellyn, Illinois 60137 17 East Monroe Street, Suite 212 Chicago, Illinois 60603 Ms. Bridget Little Rorem Appleseed Coordinator David C. Thomas, Esq.

117 North Linden Street 77 S. Wacker Drive Essex, Illinois 60935 Chicago, Illinois 60601 Mr. Edward R. Crass Michael Miller, Esq.

Nuclear Safeguards and Licensing Sidley and Austin Division One First National Plaza Sargent & Lundy Engineers Chicago, Illinois 6069f 55 East Monroe Street Chicago, Illinois 60603 George L. Edgar Newman & Holtzinger, P..

U. S. Nuclear Regulatory Comission 1615 L Street, N.W.

Resident Inspectors Office Washington, D.C.

200*

RR#1, Box 79 Braceville, Illinois 60407 Comonwealth Edison I empany Byron Station Manager Mr. Ron Stephens 4450 North German CNrch Road Illinois Emergency Services Byron, Illinois 6 % 10 and Dis, aster Agency 110 East Adams Street Illinois Dept. of Auclear Safety Springfield, Illinois 62706 Office of Nuclea" Facility Safety 1035 Outer Park ' rive Robert Neumann Springfield, Iltinois 62704 Office of Public Counsel State of Illinois Center Commonwealth Eoison Company 100 W. Randolph, Suite 11-300 Braidwood Stat on Manager Chicago, Illinois 60601 Rt. 1, Box 34 Braceville, I'linois 60407 EIS Review Coordinator Environmental Protection Agency Chairman, Og'.e County Board Region V Post Office Eox 357 230 S. Dearborn Street Oregon Illinois 61061 i

Chicago, Illinois 60604 Chairman Attorney General Will Cout Board of Supervisors 500 South 2nd Street Will Coun./ Board Courthouse Springfield, Illinois Joliet, I'linois 60434

,.v

---,,w

..-- ~. -

,-v

,n

,-n

~,

-n,

~.., -..

November 12, 1991 Docket No. 50-344 Mr. James E. Cross Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

Dear Mr. Cross:

SUBJECT:

KRC GENERIC LETTER (GL) 89 13 " SERVICE WATER SYSTEM PROBLEliS AFFECTING SAFETY-RELATED EQUIPMENT," DATED ilULY 18, 19E9 (TAC NO M 4075)

By letter dated October 1, 1990, Portland General Electric Company submitted the second of two required responses to the subject generic letter for the Trojan Nuclear Plant. You have implemented each of the five recommended actions of GL 89-13, or an equally effective alternative course of action for one or more of them.

Your response fulfills the reporting requirements of the generic letter. This item is closed.

We remind you that, if a licensee or applicant chooses a source of action different from the recommended actions of the generic letter, the licensee or applicant should document and retain in appropriate plant records a justification that the heat removal requirements of the service water system are satisfied by use of the alternative program.

Sinccrely, Original ?:=: L, Lawrence E. Kokajko, Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:

Docket File OGC NRC & LPDRs EJordan(MNEB3701)

PD5 r/f AChu(14D1)

BBoger ACRS(10)(P315)

MVirgilio PD5 p/f RCesaro RZimmerman,RV(4) h?P D m e n y,-

5 fui LKokaj ko 9112040240 911112 i

PDR ADOCK 05000344 r 4 q r. y g P

PDR

s. v. t -

OFC

PDV/LA
PDV/ i
PDV/D

......:.._____....____:.....____.___:..__. 4L),.....:..........__..:_..___.....__.

RCe g # < soka
TQuay'I

......:......____.... 4......jko NAME f

DATE :lf /f /91

$/f/91
U/ P'/91 0FFICIAL RECORD COPY 3 pe l l

Docurent Name: TROJAN LTR/74075 40

I

[pp *

  • c t,g*'cq UNITED STATES E'

ij NUCLEAR REGULATORY COMMISSION

.c,

.p W ASH WGTON, D. C. 20555

)

f 8

%, v g November 12, 1991 l

l Docket No. 50-344 Mr. James E. Cross Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portlar.d, Oregon 97204 l

Dear Mr. Cross:

l

SUBJECT:

NRC GENERIC LETTER (GL) 89-13, " SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-FELATED EQUIPMENT,' DATED JULY 18, 1989 l

(TAC NO. 74075) i Ey letter dated October 1,1990, Portland General Electric Company submitted the second of two required responses to the subject generic letter for the Trojan Nuclear Plant.

You have implemented each of the five recommended actions of GL 89-13, or an equally effective alternative course of action for one or more of them. Your response fulfills the reportirg requirements of the Seneric letter. This item is closed.

Ke remind you that, if a licensee or applicant chooses a source of action different from the recomended actions of the generic letter, the licensee or applicant should document and retain in appropriate plant records a justification that the heat removal requirements of the service water system are satisfied by use of the alternative program.

Sincerely,

.J/6&-

Labence E. Kokajko, Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc: See next page

,y Mr. James E. Cross Portland General Electric Company Trojan Nuclear Plant cc:

Senior Residerit inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Fost Office Box 0 Rainier, Oregon 97048 Mr. Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. David Stewart-Smith Oregon Department of Energy Salem, Oregon 97310 Regior.al Administrator, Region V U.S. Nuclear Regul6 tory Commission I

1450 Maria t.ane, Suite 210 Walnut Creek, California 94596 Mr. Tom Walt General Manager, Technical Functions Trojan fiuclear Plant 71760 Columbia River Highway Rainier, Oregon 97048 j

l 1

i l