ML20054H863

Summary of 820608-10 Meetings W/Util in Washington County,Ne Re Procedures & Operator Training Dealing W/Pressurized Thermal Shock.Viewgraphs Encl

ML20054H863
Person / Time
Site:	Fort Calhoun
Issue date:	06/16/1982
From:	Tourigny E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8206250105
Download: ML20054H863 (21)

Text

g k~ h c.w w V W wm Me JUN 161982 Docket No. 50-235 LICEf!SEE: Omaha Public Power District (0 PPD)

FACILITY: Fort Calhoun fluclear Power Station, Unit 1 SURJECT: SUTARY OF JUNE 8-10, 1932 MEETING WITH OPPD, NRC STAFF, AND NRC CONTRACTOR PERSONNEL. REGARDING PROCEDURES AND OPERATOR TP.AINING DEALING WITH PRESSURIZED THERifAL SHOCK Introduction The necting was held at the Fort Calhoun Nuclear Power Station located in Washington County, Nebraska. An exit meeting was held at the OPPD engineering offices located in Omaha, Nebraska. The meeting was held on June 8-It', 1982 at the request of HRC staff. The purpose of the meeting was to audit the Station's operating and caergency procedures and operator training as they apply to pressurized Thernal Shock (PTS). The NRC Fort Calhoun Station Project !!anager conducted the meeting, and was assisted by.the NRC Fort Calhoun Station Senior Resident Inspector. The detailed review of procedures and training and operator interviews were conducted by the NRC contractor, Battelle Pacific Northwest Laboratories. The OPPD participants were corporate officials, plant management officials, and select Station Technical Advisors (STA's), Senior.Reacter Operators (SR0's), and Reactor Operators (R0's). The detailed agenda for the meeting is contained in enclosure 1. Enclosure 2 identifies the aceting attendees.

Addetailed report regarding the neeting is expected to be foniarded frca the NRC contractor to the NP.C staff shortly. A summary of the meeting follows.

Summary Five general recorrendations regarding procedures and control room instrumentation were made by the NRC contractor. These were:

(1) The value of a certain paraneter should be consistent throughout all instructions and procedures. Slight inconsistencies were found; (2) flinimum and maxit'un subcooling t'emperatures should be used in the caergency procedures. In some procedures, only minimum subcooling temperatures were given; (3) Use only one saturation cur've in the energency procedures. Two differen curves are presently in the procedures: one has temperature versus pressure whereas the other has pressure versus temperature; 8206250105 820616 PDR ADOCK 05000285 P PDR OFFICE ) ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . .

c unnue > . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

ourp . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

ne ronu sis oog emeu ono OFFICIAL RECORD COPY usoco: mi-mwo

)

J \.,

.. #- 4

-2 (4) The current flDT curhe should be in every procedure that refers to it. This is presently not the case; and (5) Theoperatorsshouldbeprohidedwithamethodfordeterminingthe subcooling margin for when the.RCS temperature drops below 4650 F.

This is presently not the case.

fio general recomeddations were made insofar as oper$ tor tr$1ning.and l

operator interviews were concerned. Regarding operator training as it relates to PTS, a one hour videotape uns presented as an example of PTS training. The corresponding handout is contained in enclosure 3.. Con-( corning interviews, two STA's, two SR0's, and two R0's were intervicued.

The !!RC. project nanager advised the District's management officials that the above recorrendations were f;RC contractor recomendations and not f;RC recorrendations or requircaents at this time.

E. G. Tourigny, Project fiangger Operating Reactors Eranch ?3 Division of Licending Enclosures

1. iigenda 2 Attend mce list

3. PTS Training Passout cc w/enclosurcs:

See next page

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ac ronu ais oo.aomscu cao OFFICIAL RECORD COPY usa m m - m m

E _ . . . _ _. .. . -

MEETING

SUMMARY

DISTRIBUTION Licensee:

• Copies also sent to those people on service (cc) list for subject plant (s).

Dccket File NRC PDR L PDR NSIC TERA ORB #3 Rdg JHeltemes BGrimes -

RAClark Project Manager PMKreutzer OELD I&E ACRS-10 1 l

ORB #3 Summary File NRC Participants g O, g G #.$

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1 F

i Omaha Public Power District cc:

Marilyn T. Shaw, Esq.

LeBoeuf, Lamb, Leiby & MacRae

,1333 New Hampshire Avenue, N.W.

Washington, D. C. 20036 Mr. Jack Jensen Chairman, Washington County Board of Supervisors Blair, Nebraska 68023 U.S. Environmental Protection Agency Region VII

ATTN

Regional Radiation l

Representative 324 East lith Street '

Kansas City, Missouri 64106 Mr. Frark Gibson W. Dale Clark Library 215 South 15th Street Omaha, Nebraska 68102 i

S Alan H. Kirshen, Esq.

I Fellman, Ramsey & Kirshen

• i 1166 Woodmen Tower j Omaha, Nebraska 68102

[ Mr. Larry Yandel.1 U.S.N.R.C. Resident Inspector 1 P. O. Box 309 Fort Calhoun, Nebraska 68023

)

Mr. Charles B. Brinkman Manager - Washington Nuclear Operations

, C-E Power Systems Combustion Engineering, Inc.

4853 Cerdell Avenue, Suite A-1 Bethesda, Maryland 20014 Regional Administrator Nuclear Regulatory Commission, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Enclosure 1 i

I i ' . Aoenda

~

l Ft. Calhoun - PTS

June 8. 9, 10

. Tuesday, June 8 i

t Horning -

i Short meetina with plant manaoement to outline purpose of visit.

I Meet with training staff to review PTS training outline and i training program.

Afternoon

! Review procedures j Review Ft. Calhoun thermal transients.

Schedule interviews with operations personnel. Minimum of l 2 RO's, 2 STA's and 2 SRO's (one of which is a shift supervisor).

j j Tour control room.

Wednesday, June 9 ,

i Interview operations personnel.

Discuss cuestions on procedures. . ~ ~ ~ ~

t Discuss thennal ' transients.

i j Thursday, June 10 Morning

~~

Complete operations interviews (if needed).

l Meet with project manager and resident to discuss exit interview.

i -

Afternoon Exit interview. .

t

' ~ "

s

• Enclosure 2 I

I I Attendance List NRC E. Tourigny, PM

. L.yandell, SRI BPNL B. Clark K. Ames B. Rankin OPPD W. Jones K. Vorris R. Jaworski R. Andrews W. Gates T. Patterson R. Short J. Gass L. Kusek J..Fleuhr F. Swihel A. Richards l 2 STA's

! 2 SR0's 2 RO's i.

t _- - . . . . . _ _ . . m__ . ..

.;. Enclosure 3 REACTOR VESSEL PRESSURIZED THERMAL SH0CK ELEMENTS VESSEL STEEL WITH HIGH RTNDT Weld material NDTT had increased by approximately 250 F on 1/1/82 Plate Material NDTT had not increased significantly.

High Copper Content (0.35%)

High Neutron Fluence THERMAL SH0CK DUE T0.C00LDOWN Stuck Open Safety Steam Line Break Small Break LOCA STRESS DUE TO REPRESSURIZATION High Pressure Injection Pumps

- Charging Pumps J

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I EMERGENCY PROCEDURE ACTIONS

1. ACHIEVE 200F SUBC00 LING USING MAXIMUM TEMPERATURE IN RCS II. TERMINATE CHARGING AND HPSI FLOW IF

1) 20 F SUBC00 LING IS ACHIEVED

2) PRESSURIZER WATER LEVEL IS ABOVE HEATER CUTOFF III. MAINTAIN COLDEST RCS TEMPERATURE AND PRESSURE WITHIN THE ALLOWABLE C00LDOWN CURVE RANGE

1) USE AUXILIARY SPRAY TO DEPRESSURIZE

2) RESTART RCP IN INTACT LOOP IV. DO NOT REPRESSURIZE SYSTEM

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RCS PRESS-TEMP LIMITS C00LDOWN 6.1 EFPY.

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