ML20056D988

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Summary of 930715 Meeting W/Util Re Shutdown Cooling Alternatives During Next Refueling Outage.Attendance List & Handouts Encl
ML20056D988
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/02/1993
From: Wigginton D
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9308190146
Download: ML20056D988 (23)
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  1. 1 ' It UNITED STATES j .j NUCLEAR REGULATORY COMMISSION  :

! WASHINGTON. D.C. 205554X)01 s [

'% [,, ,, #g August 2, 1993 Docket No. 50-382 LICENSEE: Entergy Operations, Inc.

FACILITY: Waterford Steam Electric Station, Unit No. 3

SUBJECT:

SUMMARY

OF MEETING HELD ON JULY 15, 1993, WITH ENTERGY OPERATIONS, INC., TO DISCUSS SHUTDOWN COOLING ALTERNATIVES DURING THE NEXT REFUELING OUTAGE On July 15, 1993, the NRC staff met with the licensee for the Waterford Steam Electric Station, Unit No. 3 (Waterford 3), to discuss alternatives under t consideration for shutdown cooling at the next refueling outage, presently scheduled for the spring of 1994. The meeting had been requested by the licensee sufficiently in advance of the refueling outage to allow for  ;

discussion of plans to meet the Commission's expectations for adequate 'i shutdown cooling. Enclosure I contains a list of meeting attendees. t Enclosure 2 contains the handouts from which the licensee's presentation was -r made.  :

Two areas of discussion stood out. First, the licensee will calculate the risk profile with an integrated ORAM-TIP/DAIL-CAFTA model to determine what ,

time, initiators, and equipment are important during shutdown and to schedule the outage work accordingly. Entergy Operations, Inc., is the first licensee i to use the integrated model approach. i Second, the licensee has considered a number of options for providing shutdown cooling. These include a temporary emergency diesel generator for the  :

injection mode, a temporary emergency diesel generator for recirculation, the i safety injection tanks (SITS)-for gravity feed, emergency power from l Waterford 1 or 2, diesel-driven water pumps, and the use of fire pumps. The licensee's task force narrowed these options down to the recirculation-mode temporary diesel generator or gravity feed from the SITS. .

The license then performed an analysis, assuming worst-case conditions, to j establish a technical basis from which to further analyze these two options. . 1 In addition, the licensee reviewed industry studies on shutdown cooling and .

electrical power events. The licensee concluded:  :

1

1. _The temporary diesel could provide cooling capacity for several i hours depending on fuel capacity. Based on industry experience, <

this n uld be more than sufficient time to reestablish primary i electrical power. i

2. The SITS could inject water into the core quickly enough to prevent boiling. When fully injected, the SITS, under worst-case conditions, would provide cooling and water capacity to prevent '

boiling and core uncovery for slightly more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Based on industry experience, the licensee is highly confident that primary  ;

O4001y, 5 electrical power would be reestablished.

3. b P

DD O O 82-PDR

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3. The SITS allow operators to utilize familiar plant equipment and do not require additional training or special skills. To operate ,

the diesel, however, special procedures and training were necessary.

4. Neither option posed additional safety concerns for plant operators. -
5. Based on industry experience with shutdown cooling disruptions, the SITS provide an additional safety benefit in that they can provide cooling i'or a much broader range of shutdown cooling perturbations, while the benefits of the diesel are realized only for the far more infrequent total loss of power event.

Based on the above evaluation, the licensee proposed using the SITS as an additional level of protection above their commitment to (and understanding of) the NUMARC guidelines and that required by the technical specifications.

The staff was not prepared to respond to the new option of using the SITS but did note that 1) a number of questions on SIT operation may need to be answered at a subsequent meeting, 2) recent analysis shows that gravity feed from even larger sources such as the refueling water storage pool may not be enough to offset the requirement for a second emergency diesel generator, and '

3) the staff's current recommendation is that at least one offsite and two emergency sources of onsite power are needed whenever there is fuel in the core and the water level is less than 23 ft above the reactor vessel flange.

The staff was preparing to discuss the overall problem with the Commission on July 20, 1993, and will advise the licensee following that meeting.

The licensee and the staff will continue to discuss the options after the licensee has reviewed the SECY paper to be discussed at the July 20, 1993, Commission meeting.

ORIGINAL SIGNED BY:

David L. Wigginton, Senior Project Manager .

Project Directorate IV-1 Division of Reactor Projects - III/IV/V '

Office of Nuclear Reactor Regulation t

Enclosures:

1. List of attendees DISTRIBUTION w/ enclosures: i
2. Handout Docket File NRC & Local PDRs PD4-1 Reading A. B. Beach, RIV cc w/o Enclosure 2: D. Wigginton i See next page i w/o Enclosure 2:  !

T. Murley/F. Miraglia J. Partlow ,

J. Roe E. Adensam  ;

H. Rood P. Noonan [

NRC Participants

' ~

OGC ACRS (10) J. Mitchell, ED0 OFC LA:PD4-Y"M4 _ PhM1 SRX.B // D(A):PD4-1 NAME PNoona Dhg ton:pk R/oYe( HRood [ M #

DATE Q /.N93 7/N93 '//N93 T / 2. /93 ,

COPY YES/M [E}/NO - kE)/N0 YES/NO Document Nam'ET' WATJulI3.mts -

3. The SITS allow operators to utilize familiar plant equipment and do not require additional training or special skills. To operate the diesel, however, special procedures and training were necessary.
4. Neither option posed additional safety concerns for plant operators.
5. Based on industry exp & nce with shutdown cooling disruptions, the SITS provide an additional safety benefit in that they can provide cooling for a much broader range of shutdown cooling perturbations, while the benefits of the diesel are realized only for the far more infrequent total loss of power event.

Based on the above evaluation, the licensee proposed using the SITS as an additional level of protection above their commitment to (and understanding of) the NUMARC guidelines and that required by the technical specifications.

The staff was not prepared to respond to the new option of using the SITS but did note that 1) a number of questions on SIT operation may need to be answered at a subsequent meeting, 2) recent analysis shows that gravity feed from even larger sources such as the refueling water storage pool may not be enough to offset the requirement for a second emergency diesel generator, and

3) the staff's current recommendation is that at least one offsite and two emergency sources of onsite power are needed whenever there is fuel in the core and the water level is less than 23 ft above the reactor vessel flange.

The staff was preparing to discuss the overall problem with the Commission on July 20, 1993, and will advise the licensee following that meeting.

The licensee and the staff will continue to discuss the options after the licensee has reviewed the SECY paper to be discussed at the July 20, 1993, Commission meeting.

ORIGINAL SIGNED BY:

David L. Wigginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Enclosures:

1. List of attendees DISTRIBUTION w/ enclosures:
2. Handout Docket File NRC & Local PDRs PD4-1 Reading A. B. Beach, RIV cc w/o Enclosure 2: D. Wigginton See next page w/o Enclosure 2:

T. Murley/F. Miraglia J. Partlow J. Roe E. Adensam H. Rood P. Noonan OGC NRC Participants ACRS (10) J. Mitchell, EDO 0FC LA:PD4-Y"M4 Ph81 SRXB // D(A):PD4-1 NAME PNoona h D h h ton:pk R/oYed HRood [ M F DATE Qd[f93 '7/N93 1/M93 T/Z/93 COPY YES/M h/NO M/NO YES/NO Document Nam W WATJulf5.mts

l .~

3. The SITS allow operators to utilize familiar plant equipment and do not require additional training or special skills. To operate the diesel, however, special procedures and training were necessary.
4. Neither option posed additional safety concerns for plant operators.
5. Based on industry experience with shutdown cooling disruptions, the SITS provide an additional safety benefit in that they can provide '

cooling for a much broader range of shutdown cooling perturbations, ,

while the benefits of the diesel are realized only for the far more infrequent total loss of power event.

Based on the above evaluation, the licensee proposed using the SITS as an additional level of protection above their commitment to (and understanding of) the NUMARC guidelines and that required by the technical specifications.

9 The staff was not prepared to respond to the new option of using the SITS but~

did note that 1) a number of questions on SIT operation may need to be answered at a subsequent meeting, 2) recent analysis shows that gravity feed from even larger sources such as the refueling water storage pool may not be enough to offset the requirement for a second emergency diesel generator,-and '

3) the staff's current recommendation is that at least one offsite.and two emergency sources of onsite power are needed whenever there is fuel in the core and the water level is less than 23 ft above the reactor vessel flange.

The staff was preparing to discuss the overall problem with the Commission on j July 20, 1993, and will advise the licensee following that meeting.

The licensee and the staff will continue to discuss the options after the licensee has reviewed the SECY paper to be discussed at the July 20, 1993, .;

Commission meeting.  ;

Q David L. Wigginton, Senior Project Manager  :

Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation i

Enclosures

1. List of attendees
2. Handout cc w/o Enclosure 2:

See next page j l

t

-l Entergy Operations, Inc.

Waterford 3 cc:  !

Mr. Hall Bohlinger, Administrator Regional Administrator, Region IV Radiation Protection Division U.S. Nuclear Regulatory Commission  !

Office of Air Quality and Nuclear Energy 611 Ryan Plaza Drive, Suite 1000 ,

Post Office Box 82135 Arlington, Texas 76011 '

Baton Rouge, Louisiana 70884-2135  :

Resident Inspector /Waterford NPS i Mr. John R. McGaha Post Office Box 822 i Vice President, Operations Killona, Louisiana 70066  ;

Support .

Entergy Operations, Inc. Parish President Council P. O. Box 31995 St.~ Charles Parish -

Jackson, Mississippi 39286 P. O. Box 302 Hahnville, Louisiana 70057- -

William A. Cross  :

Bethesda Licensing Office Mr. Harry W. Keiser, Executive Vice-  !

3 Metro Center President and Chief Operating ,

Officer Suite 610 - Entergy Operations, Inc. >

Bethesda, Maryland 20814 P. O. Box 31995 _

Mr. Robert B. McGehee f Wise,-Carter, Child & Caraway Chairman P.O. Box 651 Louisiana Public Service Commission '

Jackson, Mississippi 39205 One American Place, Suite 1630 t Baton Rouge, Louisiana- 70825-1697 Mr. D. F. Packer

  • General Manager Plant Operations Mr. R. F. Burski, Director-  :

Entergy Operations, Inc. Nuclear Safety .

P. O. Box B Entergy Operations, Inc.:  ;

Killona, Louisiana 70066 P. O. Box B' i Killona, Louisiana 70066 l Mr. L. W. Laughlin, Licensing Manager '

Entergy Operations, Inc. Mr. Ross P. Barkhurst P. O. Box B Vice President Operations Killona, Louisiana 70066 Entergy Operations,-Inc. .

P. 0. Box B' Winston & Strawn Killona, Louisiana 70066

-Attn: N. S. Reynolds l 1400 L Street, N.W.  ;

Washington,-DC 20005-3502

-1 1

_ . _ . . -. _. . - .I

l' Enclosure 1 July 15.1993 l

Meetina with Enterov Operations. Inc.

Shutdown Coolina Alternatives For Next Refuelina Waterford Steam Electric Station. Unit No. 3 List of Attendees ,

Terence L. Chan NRC/NRR D. Wigginton NRC/NRR [

Ross Barkhurst E01 E. G. Adensam NRR/NRC -

R. C. Jones NRC/NRR Jack Roe NRC/NRR l Chu-Yu Liang NRC/NRR/SRXB Robert S. Starkey E0I Daniel F. Packer E01 I l

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Enclosure 2 REDUCED INVENTORY DURING RE UEL OUTAGE 6 PURPOSE OF MEETING

. EMPHASIS PLACED ON SDC AT W3 SDC/0RA TASK FORCE HISTORY

. OVERVIEW 0F ANALYSES / PLANS FOR REDUCED INVENTORY OPERATIONS DURING RF6 ACTIONS PLANNED /0N-G0ING

^

PLANS FOR RF6 O

t 1

l 4

l

REDUCED INVENTORY DURING ,

REFUEL OUTAGE 6 SDC/0RA TASK FORCE HISTORY l

SDC TASK FORCE ESTABLISHED IN OCTOBER-1988 PURPOSE -

REVIEW INDUSTRY EVENTS REVIEW ADEQUACY OF PROCEDURES, EQUIPMENT AND TRAINING

= MET OVER 50 TIMES DEVOTING OVER 25,000 MAN-HOURS

. AREAS OF INVOLVEMENT  :

ADMINISTRATIVE CONTROL / PROCEDURE  ;

ENHANCEMENT -

RCS LEVEL SYSTEM DESIGN / INSTALLATION- .

NUMEROUS SDC.RELATED ANALYSES  !

INTERNAL' AUDIT OF SDC ACTIVITIES i 1

i i

REDUCED INVENTORY DURING REFUEL OUTAGE 6 i

SDC/0RA TASK FORCE HISTORY (CONT.) f TECHNICAL SPECIFICATIONS INDUSTRY SURVEYS / EVENTS REVIEW 0F OUTAGE PLANNING ,

l TRAINING  ;

I

. SCOPE INCREASED IN MARCH 1991 TO INCLUDE OUTAGE RISK ASSESSMENT- ,

RISK MANAGEMENT OF SHUTDOWN 0PERATIONS OVERALL OUTAGE PHILOSOPHY  ;

PRECURSORS TO EVENTS HUMAN PERFORMANCE INDUSTRY EXPERIENCE G0 BEYOND TECHNICAL SPECIFICATION j REQUIREMENTS  ;

1

4 8 9 O

REDUCED INVENTORY DURING REFUEL OUTAGE 6 SDC/0RA TASK FORCE HISTORY-(CONT.)

IMPLEMENTATION OF NUMARC'S SHUTDCWN MANAGEMENT GUIDELINES (91-06) 1 l'

4 i

I

REDUCE) INVENTORY DUR::hG REFUEL OUTAGE 6 ACTIONS PLANNED /0N-G0ING l . INTEGRATING ORAM-TIP/DAIL-CAFTA FOR W3 l

AGAIN TAKING PROACTIVE APPROACH FOR SDC FIRST PLANT TO USE INTEGRATED MODEL OPTIMIZE OUTAGE SCHEDULE TO MINIMIZE RISK AND ENHANCE SAFETY l -

EVALUATE OUTAGE AT COMPONENT LEVEL OF DETAIL CALCULATE RISK PROFILE TO DETERMINE i WHAT TIME, INITIATORS, AND EQUIPMENT

! ARE IMPORTANT EXTEND AND FOCUS OUTAGE RISK MANAGEMENT GUIDELINES SCHEDULED COMPLETION OF 12/31/93 5

.. s REDUCED INVENTORY DURING  !

REFUEL OUTAGE 6 1 3

ACTIONS PLANNED /0N-G0ING (CONT.)  ;

. ESTABLISHED TASK FORCE TO RECOMMEND PLAN FOR RF6 i ESTABLISHED AS A RESULT OF LATE i DISCUSSIONS PRIOR TO RF5 ,

- MEMBERS FROM OPERATIONS, MAINTENANCE, -

ENGINEERING, SAFETY ANALYSIS, P&S AND  !

LICENSING  :

OPTIONS CONSIDERED .

TED FOR INJECTION l TED FOR RECIRCULATION  !

SAFETY INJECTION TANKS (SIT'S); -

POWER FROM W1&2 -

DIESEL. DRIVEN WATERLPUMP  ;

USE OF FIRE PUMPS l 6

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1 i

REDUCED INVENTORY DURING 1 REFUEL OUTAGE 6  :

i ACTIONS PLANNED /0N-G0ING (CONT.)  :

PURCHASE NEW DIESEL / POWER SOURCE l

PRESSURIZING RWSP l DEVELOP NEW GRAVITY FEED METHOD q

OPTIONS NARROWED i I

TED/ RECIRCULATION - SDC MODE l GRAVITY FEED FROM SIT'S -!

ae TED/ RECIRCULATION  !

1 PRO'S RESTORE SDC j

COOL CORE:AS LONG AS FUEL j SUPPLY LASTS i

' t NO SPILLAGE-IN CONTAINMENT .

i I

1 7 ,

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REDUCED INVENTORY DURING REFUEL OUTAGE 6 ACTIONS PLANNED /0N-GOING (CONT.)

CON'S ONLY GOOD FOR LOSS OF POWER EVENTS (ONLY 1/3 POWER RELATED)

MUST ESTABLISH NEW PROCEDURES /

TRAINING SIT'S l

PR0'S IN PLACE OPERATORS HAVE EXPERIENCE t -

CAN BE USED FOR NON-POWER.

RELATED EVENTS INCREASE TIME TO BOILING TO 90 MINUTES-L 1

8 I'

C - - - - - -_ . .

s REDUCED INVENTORY DURING  :

I REFUEL OUTAGE 6 ACTIONS PLANNED /0N-G0ING (CONT.)

CON'S i o

SOME SPILLAGE OF REACTOR  :

COOLANT INTO CONTAINMENT COULD-  !

OCCUR 8

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1

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.. a REDUCED INVENTORY DURING  ;

1 REFUEL OUTAGE 6 l

i PLANS FOR RF6 1 i

. PLANT CONDITIONS MID-LOOP /N0ZZLE DAMS ON 7TH DAY  :

i SECOND DRAINDOWN TO MID-LOOP ON i 31ST DAY j ONE EDG AND TWO INDEPENDENT OFF-SITE j POWER SOURCES (EXCEEDING T.S. AND 1 MEETING NUMARC) .

ANALYSIS FOR MOST LIMITING RF6 CONDITIONS OPEN HATCH N0ZZLE. DAMS MID-LOOP ON 7TH DAY-15 MIN. TO BOILING-

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-pe * ..

m+_ 4_ 4 ~ 2 - 4 s .- , -u& E..

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REDUCED INVENTORY DURING REFUEL OUTAGE 6 3

PLANS FOR RF6 (CONT.)

I

. ADMINISTRATIVE CONTROLS i CONTROL OF WORK ACTIVITIES WHILE AT- I REDUCED INVENTORY  !

l AGREEMENT TO ASSURE OFF-SITE POWER j AVAILABILITY-I MOVEMENT OF VEHICLES ON-SITE l

. CONTAINMENT-CLOSURE  !

INSIDE SEAL- j u

NO EQUIPMENT IN HATCH DURING MID-LOOP TRAINED AND DEDICATED.. CREW POISEDLTO)

CLOSE a

-DEMONSTRATED CLOSURE WITHIN 17 MINUTES:

11 r

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REDUCED INVENTORY DURING  :

. REFUEL OUTAGE 6 l PLANS FOR RF6 (CONT.) i

. ASSESSMENT 0F RF6  !

OUTAGE RISK ASSESSMENT TEAM (0 RAT) j REVIEW 0F SCHEDULE  :

i ORAT MEMBERS INCLUDE.

  • CHAIRMAN - DE ENGR DEPT MEMBER - SCHEDULING DEPT i MEMBER - OE ENGR DEPT .
  • MEMBER:--OPS DEPT  :

MEMBER - MOD CONTROL DEPT  !

  • HOLDS 0R HAS HELD PLANT SPECIFIC l

SR0 LICENSE i

ITEMS OF' CONCERN-GENERATED WILL BE' j RESOLVED-PRIOR TO SCHEDULE APPROVAL. j i

ASSESSMENT ITEMS REVIEWED BY PORC:

AND. GENERAL' MANAGER, PLANT OPERATIONS:

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~,m ,- -y v ., 4 --.,- , .-- , en - , e - ++ . - - -- I.

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REDUCED INVENTORY DURING REFUEL OUTAGE 6 PLANS FOR RF6 (CONT.)

ORAM-TIP/DAIL-CAFTA WILL BE USED AS -

AN AID IN DEVELOPING SCHEDULE REVISIONS TO OUTAGE SCOPE WILL BE REVIEWED BY ORAT j

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I 13

REDUCED INVENTORY DURING REFUEL OUTAGE 6 PLANS FOR-RF6 (CONT.)

EXTRA CONTINGENCY OPTION PLANNED FOR LOSS OF SDC l l

HAVE ALL FOUR SIT'S AVAILABLE TO GRAVITY FEED RCS DEDICATED PERSONNEL READY TO OPERATE VALVES FOR LOSS OF POWER EVENT j PREVENT BOILING FOR 90 MINUTES DURING WORST CASE DRAINDOWN ACCOMMODATE LOSS OF POWER RELATED l LOSS OF SDC EVENTS PLUS OTliERS 14

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