ML20147J208

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Summary of 970403 Meeting W/Illinois Power Co in Rockville, MD Re Licensee Amend Application on Degraded Voltage Instrumentation for Clinton Power Station.List of Attendees & Copy of Handouts Encl
ML20147J208
Person / Time
Site: Clinton Constellation icon.png
Issue date: 04/09/1997
From: Pickett D
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-M98039, NUDOCS 9704110129
Download: ML20147J208 (8)


Text

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p i UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20066-0001

%. April 9, 1997 LICENSEE: Illinois Power Company (IP)

FACILITY: Clinton Power Station

SUBJECT:

SUMMARY

OF APRIL 3, 1997, MEETING TO DISCUSS LICENSE AMENDMENT APPLICATION ON DEGRADED VOLTAGE INSTRUMENTATION - CLINTON POWER STATION (TAC NO. M98039)

On April 3, 1997, NRC staff members met in Rockville, Maryland, with representatives of IP. The purpose of the meeting was to discuss the licensee's letter of April 1,1997, describing proposed changes to the technical specifications. A list of meeting participants is included as Enclosure 1, and a copy of the meeting handouts is provided as Enclosure 2.

The licensee opened the meeting by making a brief presentation of the chronology of events. In the 1992 time frame, inspection findings where made that questioned the adequacy of the technical specification loss of instrumentation voltage setpoints during degraded grid conditions. With the exception of the RHR pumps, the Clinton LOCA mitigating systems receive a block start initiating signal that may result in a drop of grid voltage such that inadequate voltage may be available. In response to these concerns, the licensee installed control room annunciators and implemented administrative controls. Thus, operator actions were relied upon to ensure adequate voltage would be available for the LOCA mitigating systems. The licensee's LER 94-005 further describes these developments.

The licensee subsequently committed to long-term hardware modifications (i.e.,

install new relays and higher voltage setpoints) that would eventually terminate the need for the administrative controls. One safety-related division would be modified during each of RF6, RF7, and RF8. License Amendment No. 110, issued on December 4, 1996, approved the licensee's proposed changes.

During the current RF6 outage, the licensee installed the new instrumentation package for the Division 2 bus. However, operability problems were soon identified with regard to the newly installed regulating transformers. The licensee subsequently concluded that the original work package could not be performed during RF6 and an operability evaluation concluded that the degraded voltage instrumentation for all three safety-related divisions was inoperable.

This determination, in turn, resulted in all three emergency diesel generators being declared inoperable.

By letter dated April 1,1997, the licensee submitted a license amendment  ;

application proposing an interim solution. The interim solution, which is significantly different from that reviewed and approved by the staff, involves i

reinstating the administrative controls, leaving in newly installed relays, Eb 110M3

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9704110129 970409 PDR ADOCK 05000461 pop

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removing' the regulating transformers, and relying on~ higher voltage setpoints' in the technical specifications. .The application ~also included an.unreviewed-  !

safety: question (USQ)'in that reliance on the interim administrative controls ' .}

can potentially result inla' malfunction of equipment important to ' safety' of a j different type than previously considered in the USAR.'

i During the discussion of the: amendment application, the licensee stated that I

' they are. currently performing calculations to. reconfirm that the associated'

-3940-VAC and'3890-VAC alarms and operator action ~ points, respectivo1y, are j still adequate. 'The licensee committed to submit the.results of these i calculations in approximately-two weeks. :The: staff indicated that this information would be~needed in order to complete its reyiew.

cThe licensee stressed'the importance of rece'ving'a i prompt staff review.

Since all,three diesel generators have been declared inoperable, the license- l cannot' change operating modes until the amendment request has been approved.

'This ~could place 'the staff's review on-the licensee's critical path for plant

' restart. . In addition, the staff informed the licensee that they would not be.

permitted to restart the facility with an unresolved USQ.

Although the application had only been received the previous day, the staff did not identify any obvious shortcomings in the submittal. The staff understood ~the importance of this amendment application and indicated that they would work with the licensee in giving this application a high priority '

and performing a prompt review. j Original signed by:

Douglas V. Pickett, Project Manager ,

Project Directorate III-3 Division of Reactor Projects III/IV '

Office cf Nuclear Reactor Regulation Docket No. 50-461 1

Enclosures:

As stated i

cc w/encls: See next page Distribution: E-MAIL: S. Collins (SJC1) '

iDocketiFile D. Ross (SAM) F. Miraglia (FJM)

PUBLIC R. Zimmerman (RPZ) J.~ Roe (JWR)

PDIII-3 R/F. E. Adensam (EGAI) C. Carpenter (CAC) l

. 0GC J. Lazevnick (JJL) J. Calvo (JAC7)  !

ACRS G. Wright, RIII (GCW) G. Marcus (GHM)

J. Caldwell, RIII (JLC1) B. McCabe (BCM)

DOCUMENT NAME: G:\CLINTON\CLI98039. SUM  :

- To receive a copy of this document, Indicate in the box: "C" = Copy without enclosures "E" a= Copy with enclosures

  • N" = No copy 0FFICE- LA:PDIII-)_ C,. PM:PDIII-3cR.

NAME- CBoyle (14f ' DPicketPd '

DATE- 04/f/976 ,0,4/< /97 0FFICIAL RFCOR) COPY i r

N -

b removing the regulating transformers, and relying on h' igher voltage setpoints ' >

in'the. technical specifications. The application also included an unreviewed safety' question (USQ).in that reliance on the interim administrative controls

can potentially result in a malfunction of. equipment important:to safety of a - -

different type than previously considered in the USAR.

.During'the' discussion ~of the amendment application, the licensee stated that-they are currently performing calculations to reconfirm that the associated -

'3940-VAC and 3890-VAC alarms and operator action points,'respectively, are stil1~ adequate. The licensee committed to submit the results of-these calculations Tin approximately two weeks. The staff indicated that this information would be needed in order to complete its review.

The licensee stressed the importance of receiving a prompt _ staff review.

Since all three diesel generators have been declared inoperable, the license cannot change! operating modes until-the amendment request has been approved.

--This could place the staff's review on the licensee's critical path for plant restart. _In addition, the staff informed the licensee that they would not be permitted to restart the facility with an unresolved USQ.

Although the application had only been received the previous day, the staff did 'not identify any obvious shortcomings in the submittal. The staff understood the importance of this amendment application and indicated that they would work with the licensee in giving this application a high priority and performing a' prompt review.

Original signed by:

Douglas V. Pickett, Project Manager Project Directorate III-3 i

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation p Docket No. 50-461 i

Enclosures:

As stated i L  !

cc w/encls: See next page V

! Distribution: E-MAIL: S. Collins (SJC1) l Docket File D. Ross (SAM) F. Miraglia (FJM) l PUBLIC R. Zimmerman (RPZ) J. Roe (JWR)

PDIII-3 R/F E..Adensam (EGA1) C. Carpenter (CAC) i-OGC J. Lazevnick-(JJL) J. Calvo (JAC7) 3 ACRS G. Wright, RIII (GCW) G. Marcus (GHM)

J. Caldwell, RIII -(JLC1) B. McCabe (BCM)

L ' DOCUMENT NAME:L G:\CLINTON\CLI98039. SUM To resolve a copy of this document, Indicate in the box: "C" = Copy without enclosures "L" = Copy with enclosures l OFFI E LA:PDIII-3-_ C- PM:PDllI-3Ji_

NAME CBoyle Cf DPicke e '

DATE 04/f/97d 04/1 /97 0FFICIAL RECORD COPY I

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removing the regulating transformers, and relying on higher voltage setpoints in the technical specifications. The application also included an unreviewed safety question (USQ) in that reliance on the interim administrative controls can potentially result in a malfunction of equipment important to safety of a different type than previously considered in the USAR.

During the discussion of the amendment application, the licensee stated that they are currently performing calculations to reconfirm that the associated 3940-VAC and 3890-VAC alarms and operator action points, respectively, are still adequate. The licensee committed to submit the results of these calculations in approximately two weeks. The staff indicated that this information would be needed in order to complete its review.

The licensee stressed the importance of receiving a prompt staff review.

Since all three diesel generators have been declared inoperable, the license cannot change operating modes until the amendment request has been approved.

This could place the staff's review on the licensee's critical path fcr plant restart. In addition, the staff informed the licensee that they would not be permitted to restart the facility with an unresolved USQ.

Although the application had only been received the previous day, the staff did not identify any obvious shortcomings in the submittal. The staff understood the importance of this amendment application and indicated that they would work with the licensee in giving this application a high priority and performing a prompt review.

b T sh V Douglas V. Pickett, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosures:

As stated cc w/encls: See next page 4

Clinton Power Station,. Unit,No.-1 Illinois Power. Company cc:

Mr. Wilfred Connell Illinois Department .

Vic'e President of Nuclear Safety Office of Nuclear Facility Safety Clinton Power Station

. Post Office Box 678 1035 Outer Park Drive-Clinton, Illinois 61727 Springfield, Illinois 62704 Mr. Daniel P. Thompson Mr. Paul J. Telthorst Manager Nuclear Station Director - Licensing Engineering Department Clinton Power Station Clinton Power Station P. O. Box 678 Post Office Box 678 Mail Code V920~

Clinton,-Illinois 61727. - Clinton, Illinois 61727 Resident Inspector U.S. Nuclear Regulatory Commission RR#3, Box 229 A Clinton, Illinois 61727 Mr. R.-T. Hill Licensing Services Manager General Electric Company 175 Curtner Avenue, M/C 481 San Jose, California 95125 Regional Administrator, Region III l U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Chairman of DeWitt County c/o County Clerk's Office DeWitt County Courthouse

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Clinton, Illinois 61727

Mr. J. W. Blattner Project Manager j Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 j

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g? MEETING ATTENDEES APRIL 3, 1997 ILLINOIS POWER COMPANY g[ ,

i Paul.Telthorst Doug Pickett

  • oTom Elwood Jim Lazevnick.

Jerry Ray Y

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Enclosure 1 l

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, Chronology of License Amendment Development, Operability Determination Program, '

and Safety Evaluation issues i Date ," vent 1992-1994 1992 Action and LER 94-005 Established operator action / alarm No safety or operability evaluation 1995-1996 Conceptual Design of Modifications AP027, AP028, and AP029 Fall 1996 Operability Determination Program Established (CPS Procedure 1014.06)

December 1996 License Amendment 110 January / February 1997 Regulating Transformer Problem /AP032 February / March 1997 Discussions with NRC I

February-March 1997 Prepared 10CRF50.59 Safety Evaluation for crediting compensatory operator action March 1997 Prepared Technical Specification Change Package LS-97-001 March 1997 Unreviewed Safety Question (USQ) determination (factored into LS-97-001) for Modes 1,2, and 3

! March 26,1997 Determination that degraded voltage relays are Inoperable l

l April 1,1997 Submittal of LS-97 001 l

0:OPERSELWOOD% GEN 9703. DOC ENCLOSURE 2

[ Clinton Power Station Degraded Voltage Protection l April 3,1997 Introduction Mr. Telthorst \

Opening Remarks / Purpose Mr. Telthorst

. Current Plant Status  !

Background Mr. Telthorst

  • History / Development of TS Change Package LS-97-001 l

RelatedHardwareissues Mr. Ray

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  • RAT Tap Settings Division 1 and 3 Relay Changeouts i

i N Proposed TS Change Package Mr. Elwood LS-97-001 l Long-Term Actions Mr. Ray i

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. O.WPERSELWOODWGEN9703. DOC