View source for CEO-88-080, Forwards Presentation Matl Provided to NRC During 880701 Meeting Re Power Ascension Program Status

{{Adams
| number = ML20150B169
| issue date = 07/07/1988
| title = Forwards Presentation Matl Provided to NRC During 880701 Meeting Re Power Ascension Program Status
| author name = Firlit J
| author affiliation = SACRAMENTO MUNICIPAL UTILITY DISTRICT
| addressee name = 
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000312
| license number = 
| contact person = 
| document report number = CEO-88-080, CEO-88-80, NUDOCS 8807110327
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 27
}}

=Text=
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U,f-+g suun SACRAMENTO MUNICIPAL UTIUTY DISTRICT O P. O. Box 15830. Sacramento CA 95852 1830,(910) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JUL 0 71988 CEO 88-080 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Station Pl-137 Hashington, D C. 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 POWER ASCENSION PROGRAM STATUS

==Dear Sir:==

==References:==
(A) Andognini to Crutchfield {{letter dated|date=May 17, 1988|text=letter dated May 17, 1988}}, RCP Stud Integrity NRR
                                          \
(B) Andognini to NRR {{letter dated|date=June 15, 1988|text=letter dated June 15, 1988}}, RCP leakage Action Plan Attached is a copy of the presentation material provided to members of your staff in your offices during our July 1, 1988 meeting. The presentation by Messrs. Crunk and Cranston of my staff provided a review of the current power ascension schedule and our planned adjustment to that schedule. They also discussed our assessment of continued safe plant operations. The adjusted schedule shows our planned outage for shutdown and inspection of the "C" Reactor Coolant Pump (RCP) on or about August 5, 1988, following the planned 801. power trip test.
Reference (A) provided the safety evaluation addressing RCP stud integrity.
The District performed this safety evaluation to support the decision to
.            continue cperation of the "C" RCP. Reference (B) provided The      the action plan action plan addressing "C" RCP gasket leakage and RCP stud integrity.
contains acceptance criteria for continued use of the "C" RCP studs and associated schedules and illustrztions.
The attached presentation material also includes refined schedules and
'            illustrations in support of continued safe plant operations. The refined schedule combines our planned "C" RCP maintenance and inspection following the planned 801. power trip test. As discussed, the planned schedule adjustment l            maintains previous commitments and ensures safe plant operations consistent with information previously submitted to you in the referenced l
correspondence.                                                                           go o l
8807110327 880707                                                                                  '   I PDR      ADOCK 05000312                                                                              i P                    PNU RANCHO SECO NUCLEAR GENERATING STATION O 1444o Ten Cities Road. Herald. C A 95638 97 39. c09 333 ?u5

i JUL 0 713?!
  =    1 CEO 88-080 Director of NRR                                                        The combined outage eliminates an additional shutdown cycle which we believe is more conservative with respect to nuclear safety for the following reasons:
: 1. The elimination of a cooldown and heatup cycle minimizes:
: a. challenges to fuel integrity
: b. mechanical stresses on the steam generators and turbine generators
: c. processing primary coolant and its associated radiological consequences, and
: d. unnecessary thermal cycling on other mechanical portions of the RCS, such as sleeves, nozzles and piping.
: 2. Starts, stops and tests of equipment can, in general, increase the potential challenges to safety systems.
Since training enhancement at 40% power will be completed by July 8, 1988, we intend to incrcase power to 65% on or about that date and provide operator training and familiarization for approximately 3 weeks.          The 3 weeks at 65%
power are determined to be adequate because:
* Operational activities performed at 65% power are 3ssentially the same as those performed at 40% power.
* Surveillance tests performed at 65% power are the same as those performed at 40% power.
* Operations on-shift training activities to be performed prior to exceeding 65% power are not power-level dependent, and have been performed routinely since Rancho Seco returned to power operation.
In addition, since Rancho Seco returned to power operation, Operators have gained significant experience while dealing with a number of plant transients in an effective and professional manner. These transients are tabulated below:
* 5/4/88 Tripped the plant (anticipated) during the performance of STP-660.
* 5/4/88 Performed the remote shutdown test per STP-Il54.
* 5/12/88 Performed Reactor / Turbine Startup, escalated power to 401.
* 5/12/88 Electrical grid upset. Operators took manual control of                             .
turbine generator to stabilize the plant.
___      ___._________m_.______ -__.__   _   _ _ _ _ _ _ _ _ _ _ _ - .

JUL 0 71933
  , f CEO 88-F Director of NRR
* 5/15/88 Operators manually tripped the "B" Main Feed Pump to prevent a S/G overfeed when pump speed increased rapidly due to a pump speed control problem.
* 5/23/88 Operators observed high vibration indication on the main generator bearing. It was later determined that the indicated high vibration on the main generator bearings was a result of arcing generator grounding brushes causing faulty indication.
Problem was solved when elet.trical technician changed the grounding brushes.
* 6/10/88 Electrical grid upset. Operators took manual control of turbine generator to stabilize plant.
* 6/29/88 'A' and 'B' Hain Feed Block Valves closed unexpectedly while at 45% power. Operators took action to stabilize the plant at 24% and reopen the block valves. Their immediate action prevnted a challenge to the Reactor Protection System.
* 6/30/88 The power system stabilizer failed causing main generator output voltage oscillations. Operators responded to remove the stabilizer from service.
Each Control Room operating crew will cycle through a complete 12 hour shift rotation during the 3 weeks at the 65% plateau. As discussed, 3 weeks at the 65% plateau will provide for training enhancement at a higher power (65% vs 40%) while continuing to meet our training objectives. The operating crews
.       have gained extensive hands-on experience during the 8 week plateau at 40-45%
l        power because there has been extensive manual ICS operation due to ICS and Main Feed Pump Control tuning. This tuning has been ongoing since the plant returned to power operation. Although the plant has performed well at the 40-45% power plateau, past experience indicates that the plant is more stable at 65% power.
Following the shift cycle for all crews we will increase power to the 80%
power plateau on or about July 30, 1988, in preparation for the final trip test (cutrently scheduled for August 5, 1988) and the associated EFIC testing. The approximately 1 week at 80% power will provide for initial operator familiarization and additional ICS tuning at that higher power level.
Following the 80% power trip test and subsequent planned maintenance outage, the "C" RCP studs will be examined and the gasket leakage repaired (Reference 8). He will evaluate the need to perform a subsequent inspection of the studs by November 1988.
!        The 80% and 92% power plateau durations will remain at 5 weeks in length while power ascension testing is completed.

  , *,                                                                    JUL 0 719e*
CEO 88-080 Director of NRR                                 in summary, our mid-term assessment of the Powsr Ascension program, the references, and the previous discussion support continued safe plant operations at the proposed Power Ascension profile.
Members of your staff with questions requiring additional information or clarification may contact Steve Crunk at (209) 333-2935, extension 4913.
Sincerely,
            )
7'T "
I$    &
Joseph F. Firlit Chief Executive Officer, Nuclear Attachment cc: Administrator, Region V, NRC, Halnut Creek A. D'Angelo, NRC, Rancho Seco D. Crutchfield, NRR, Washington
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(5579)
                                                                                                                                                                                                   ~
AGENDA 1
                                                                                                                                                             . . .  . .    . . BOB CROLEY                 !
m INTRODUCTION .                                                                                       ..                     .
                                                                                                                                                                        .     . STEVE CRUNK a BACKGROUND                                                                         ..      ..     .....                                           .....
         --POWER ASCENSION SCHEDULE
                                                                                                                                                              ......GREG CRANSTON a RCP STUD INTEGRITY.                                                                           ......                                            .
l                                                                                                                               . . . . . . . .                         . . . . B I LL K EM P ER m POWER ASCENSION PROGRAM.                                                    . . . . . . . . . . .
                                                                                                                                                        . . . . . . . . . . . BOB CROLEY s 

==SUMMARY==
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I PREVIOUS ADJUSTMENTS l
n  CONSERVATIVE WITH RESPECT TO NUCLEAR SAFETY a  RESULTED IN INCREASE IN TOTAL TIME REQUIREMENT PLANNED ADJUSTMENTS J
a  CONSERVATIVE WITH RESPECT TO NUCLEAR SAFETY
         - ELIMIN ATES ONE SHUTDOWN /STARTUP CYCLE
         - RCP STUD INTEGRITY M AINTAINED
         - ADEQUATE OPERATOR TR AINING/ EXPERIENCE TIME M AINTAINED a  RESULTS IN DUR ATION OF POWER ASCENSION PROGRAM OF APPROXIM ATELY 2 MONTH GREATER THAN ORIGIN ALLY PROJECTED a  COMPARISON TO TMI/ DAVIS BESSE

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POWER ASCENSION PROGRAM i
OCTOBER 16,1987 j                      ,
                    ~                                                                          FULL POWER
                                                                               ~927.
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                                                                    ~807.
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                                                                                              ~ 6/15/88
                             ~ 1/15/88
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                           - APPROXIMATELY FIVE (5) MON THS DURATION
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POWER ASCENSION PROGRAM MARCH 22,1988
                                ~
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                                     - CRITICAUTY 07.                - 6/10/88                                ~ 10/9/88 3/20/88 (1 wk)
                                          =                                                             =
APPROXIMATELY SIX (6) MONTHS DURATION
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                                                    - PO2 (7/9/88)             - PO3                  - 11/14/88
                                  - 5/12/88
                                - 5/4/88
                    - 3/30/88 v

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BALANCE PLANNED SCHEDULE ADJUSTMENT RESULTS IN
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O PREVIOUS              SAFE PLANT COMMITMENTS             OPERATIONS
               \              /         \             /
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!     u GRADUAL RETURN TO FULL POWER OPERATION a EVALU ATE READINESS OF PLANT, PROGRAMS, I        AND PEOPLE a EXTENSIVE INTEGRATED TEST PROGRAM m' OPERATIONS PERSONNEL TRAINING & EXPERIENCE a PROCEDURE B.1 A CONTROLLING DOCUMENT i

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MID-TERM ASSESSMENT TESTING PROGRAM a TESTING COMPLETED THROUGH    40% PLATEAU m   REMAINING TESTING COMPLETED BY PO2/80%
TRIP AS PLANNED i
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   ,                                                  <=m MID-TERM       ASSESSMENT OP ER ATION S PERSONNEL a COMPLETED TRAINING ENHANCEMENT AT 40% PLATEAU u   TRAINING ENHANCEMENT AT 65 % TO BE CONDUCTED DURING 3 WEEKS                '
         - TRAINING OBJECTIVES SATISFIED
         -- OPERATING EXPERIENCE AT 65% VERSUS 40%
l    m   TRAINING ENHANCEMENT AT 80 % & 92% TO BE l        CONDU CTED AS PLANNED N                                 -
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