ML20217H340

Summary of 970717 Meeting W/Util in Rockville,Md Re Issue of Degraded Grid Voltage at Plant.List of Participants & Meeting Handouts Encl

ML20217H340
Person / Time
Site:	Clinton
Issue date:	03/31/1998
From:	Hopkins J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9804030274
Download: ML20217H340 (14)

Text

.

, q March 31, 1998-

. LICENSEE: filinois Power Company -

1

. FACILITY:. Clinton Power Station j

SUMMARY

OF JULY 17,- 1997, MEETING ON DEGRADED VOLTAGE On July 17,1997, NRC management and staff met in Rockville, Maryland, with representatives of Illinois Power Companyi The purpose of the meeting was to discuss the issue of degraded grid voltage at the Clinton Power Station.- A list of the meeting participants is included as

Enclosure 1, and a copy of the meeting handout is provided as Enclosure 2.

The licensee presented information that they found signified compliance with their

- design / licensing basis. The NRC staff did not agree. The licensee stated that they would '

review this issue for the next step. ,

Original signed by:

Jon B;;Hopkins, Senior Project Manager -

Project Directorate lil-3 .

Division of Reactor Projects lil/IV  !

Office of Nuclear Reactor Regulation j Docket No. 50-461 >

Enclosures:

1. List of Meeting Participants

2. Meeting Handout -

\

cc w/encis: See next page e, O\

. DISTRIDUTION -

Y Hard Coov w/encla E-mail w/Enct 1 _

Docket File SCollins (SJC1), GKelly PD lll-3 Reading FMiraglia (FJM) JRoe PUBLIC ' THiltz GMarcus GGrant, Rlli . BBoger DSkeen JHopkins - . EAdensam DButler RSavio DThatcher Hard Conv w/Enci 1 Dross (SAM 3) NTrehan OGC JHopkins '. CMiller i ACRS JCalvo -

DOCUMENT NAMEi G:\CLINTON\071797.MTS' OFFICE - PD3-3:PM - i R PD3-3:LA F n: TE 3) > 313l -

OFFICIAL RLECORD COPY 9904030274 980331 PDR ADOCK 05000461 P ,

PDR gdgMIU in

- March 31, 1998 LICENSEE: lilinois Power Company FACILITY: Clinton Power Station

SUMMARY

OF JULY 17,1997, MEETING ON DEGRADED VOLTAGE On July 17,1997 NRC management and staff met in Rockville, Maryland, with representatives of Illinois Power Company. The purpose of the meeting was to discuss the issue of degraded grid voltage at the Clinton Power Station. A list of the meeting participants is included as Enclosure 1, and a copy of the meeting handout is provided us Enclosure 2.

The licensee presented information that they found signified compliance with their design / licensing basis. The NRC staff did not agree. The licensee stated that they would review this issue for the next step.

Original signed by:

Jon B. Hopkins, Senior Project Manager Project D! rectorate ill-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosures:

1. List of Meeting Participants

2. Meeting Handout cc w/cncis: See next page DISTRIBUTION Hard Conv w/encls E-mail w/Enct 1 Docket File SCollins (SJC1) GKelly PD lil-3 Reading FMiraglia (FJM) JRoe PUBLIC - THiltz GMarcus GGrant, Rlli BBoger DSkeen JHopkins EAdensam DButler j RSavio DThatcher Hard Coov w/Enct 1 Dross (SAM 3) NTrehan OGC JHopkins CMiller ACRS JCaNo DOCUMENT NAMEi G:\CLINTON\071797.MTS OFFICE PD3-3:PM ,

S_ PD3-3:LA F j NAME JHopkins I f EBamhill @/P l DATE 3 8//98 7 (H//98 OFFICIAL RECORD COPY-

p "%

. p+ t UNITED STATES i , g g NUCLEAR REEULATORY COMMISSION i f CASHi~;CTcN, D.C. 20665-0001 s*****/ March 31, 1998 LICENSEE: Illinois Power Company FACILITY: Clinton Power Station

SUMMARY

OF JULY 17,1997, MEETING ON DEGRADED VOLTAGE On July 17,1997, NRC management and staff met in Rockville, Maryland, with representatives of Illinois Power Company. The purpose of the meeting was to discuss the issue of degraded grid voltage at the Clinton Power Station. A list of the meeting participants is included as Enclosure 1, and a copy of the meeting handout is provided as Enclosure 2.

The licensee presented information that they found signified compliance with their design / licensing basis. The NRC staff did not agree. The licensee stated that they would review this issue for the next step.

I 0 /

Jon B. Hopkins, enior' Project Manager Project Directorate lil-3 Division of Reactor Projects Ill/IV l Office of Nuclear Reactor Regulation i 8 l Docket No. 50-461 1

Enclosures:

1. List of Meeting Participants

2. Meeting Handout cc w/encls: See next page

E Clinton Power Station, Unit 1-tilinois Power Company

~

cc:

i John G. Cook lilinois Department of Nuclear Safety Senior Vice President Office of Nuclear Facility Safety Clinton Power Station 1035 Outer Park Drive P.O. Box 678 Springfield, IL- 62704 Clinton,IL 61727 )

Joseph V. Sipek Larry Wigley Director- Licensing Manager Nuclear Station Clinton Power Station a Engineering Department P.O. Box 678 ' 3 Clinton Power Station Mail Code V920 -)

P.O. Box 678 Clinton,IL 61727 l Clinton,IL 61727 Resident inspector U.S. Nuclear Regulatory Commission RR#3, Box 229 A Clinton,IL 61727 R. T. Hill Licensing Services Manager General Electric Company 175 Cunner Avenue, M/C 481 San Jose, CA 95125 l Regional Administrator, Region ill U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Chairman of DeWitt County clo County Clerk's Office DeWitt County Courthouse Clinton,IL 61727 .

J. W. Blattner Project Manager _  !

Sargent & Lundy Engineers 55 East Monroe Street '

Chicago,IL 60603  :

s-

MEETING ATTENDEES 1

NRC AND ILLINOIS POWER COMPANY DISCUSSION OF DEGRADED GRID VOLTAGE JULY 17,1997 .

g I J. Hopkins G. Kelly J. Calvo J. Roe D. Thatcher G. Marcus N. Trehan D. Skeen ,

C. Miller

• D. Butler

• 1 lilinois Power Comoany J. Sipek D. Thompson T. Elwood W. Romberg J. Collins M. Lyon T. Wiggins P. Walberg

'by teleconference

' j 1

l Enclosure 1 '

lilinois Power (IP)

Meeting with NRC on Degraded Voltage l

July 17,1997 l

l I

i i

IP Representatives:

W. D. Rornberg Asst. Vice President D.P. Thompson Manager-Nuclear Station Engineering M. W. Lyon Asst. Plant Manager Operations J. R. Collins Director-Transmission Services J. V. Sipek Director-Licensing T. B. Elwood - Supervisor-Licensing Operations T. O. Wiggins Engineer til P. E. Walberg Engineering Group Leader-Nuclear /PRA Attachment 2

Agenda Introduction Wayne Romberg Background Jim Collins Dan Thompson Mike Lyon Design / Licensing Basis Joe Sipek Dan Thompson Issue Resolution Joe Sipek i

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1 Background  !

e Development of Issue

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Desian/Licensina Basis

. USAR Sections 3.1.2.2.8 andI5.2.2.1 describe compliance with General Design Criterion 17

. General Design Criterion 17 - Electric Power Systems "An onsite electric power system and an offsite electric system shall be provided to permit functioning of structures, systems, and components important to safety."

. CPS Compliance With Key Requirements in GDC 17

- Requirement i 1

" Electric power from the transmission network to the onsite electric l distribution system shall be supplied by two physically independent circuits (not necessarily on separate rights of way) designed and located so as to minimize to the extent practical the likelihood of their simultaneous failure under operating and postulated accident and  !

environmental conditions." )

- CPS Comoliance Separate 138kV and 345 kV offsite supplies. See diagram.

- Reauirement

" Provisions shall be included to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with, the loss of power generated by the nuclear power unit, the loss of power from the transmission network, or the loss of power from the onsite electric power supplies."

i

, - CPS Comollance

Both 138 kV and 345 kV safety transformers are fed independently

-} from the Illinois Power system. Loss of any one or the loss of emergency diesel generators or the CPS generator does not cause a loss of the other supplies.

Desian/Licensina Basis ccont.3 General Desian Criterion 17 - Electric Power Systems (Cont.)

hteoulroment

'One of these circuits shall be designed to be available within a few seconds following a loss of-coolant accident to assure that core cooling, containment integrity, and other vital safety functions are maintained."

- CPS Comoliance The ERAT (138kV system) and RAT (345kV system) are each capable l

of being continuously available to supply all safety-related loads following a LOCA.

, Recent grid voltage history demonstrates that the 138kV system voltage is more constant than that of the 345kV system.

l - Reauirement l

Each of these circuits shall be designed to be available in sufficient l time following a loss of all onsite alternating current power supplies I and the other offsite electric power circuit, to assure that specified '

acceptable fuel design limits and design conditions of the reactor

! coolant pressure boundary are not exceeded.  :

- CPS Compliance f

e Both the ERAT (138kV system) and RAT (345kV system) are immediate access circuits. However, if the voltage of either source is too low (such that the source may not be available following a plant trip), the source effectively becomes a delayed access circuit that can be recovered in a reasonably short period of time (i.e., well within the coping time established for a station blackout at CPS).

I l

Desian/Licensina Basis ccont.)

Technical Specification Reauirements

. TS LCO 3.8.1 requires 'two qualified circuits between the offsite transmission netwo* and the onsite Class 1E AC Electric Power Distribution System, and three diesel generators."

. With one offsite circuit inoperable, Required Action A.1 requires performing SR 3.8.1.1 for the OPERABLE offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, and Required Action A.2 requires restoring the inoperable offsite circuit to OPERABLE status with 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (and within 6 days from discovery of failure to meet the LCO).

• Within two offsite circuits inoperable, Required Action C.1 requires declaring required features inoperable when the redundant required features are inoperable (within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from discovery of both circuits being inoperable concurrent with inoperability of redundant features), and Required Action C.2 requires restoring one offsite circuit to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

. SR 3.8.1.1 requires verifying " correct breaker alignment and indicated power availability for each offsite circuit every 7 days."

F h

6 e

? Issue Resolution i

• Continued Compliance with Design / Licensing Basis t

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