ML20084E550

Ro:On 700706,boron Dilution Performed W/Reactor Critical & No Reactor Coolant Pump on RHR Pump in Operation.Orders Issued That Maint Work Performed Only W/Authorized Procedures Available

ML20084E550
Person / Time
Site:	Ginna
Issue date:	07/15/1970
From:	Amish K, Nelson E ROCHESTER GAS & ELECTRIC CORP.
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084E539	List: ML20084E536 ML20084E550 ML20084E709
References
NUDOCS 8304150121
Download: ML20084E550 (3)

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M Subject ilclati:n of Techni zal 7ce:ifica:icn, Sec. 3.1.1.la - July 6, 19'O Ginna Stati:n Enit N;. 1 Docket E U-244 Cn Sunday, ~u l:' E,1T0, at approxirna+ely 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, a steam ..- sq '

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rbine cace line.

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<g offim "m " H % ~"4 n""orgerr.e. *s maic to remcVe the turbine-generator f[ci unit frcrn cer 1ce. y.OF . '

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The C.oeraticnc Encineer Nen orcceeded to .olan further rnaintenance

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during thic chutacwn, namely, :c add pack . to pressurizer cpray 7alve ..g, Q' C.!p V I

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to adjust : 1e ;;rbine trip pilot car /e. The Cperaticnc r.ngineer rernainea at .

the plant t'.rcugh u: the chutdown and the return to the normal le"el of pcwer $h.0 f .ss .,y-generaticn. . a" -- 4

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The load war gradually reduced on the turbine. Baron concentration was incresced in the prima" ' Icop, rnaintaining the "D" control rod bank at tu6m. . ,

140-180 stero cut uc"ing Se :crbbe unlcadlw ceriod. Prior to boration, the boron concentraticn in the reactcr coolant was 1093 p.om E.

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. . .:s The Shift Foreman outlined to the assembled maintenance force the  : 'i work that was to be accomplished and the coordination that was required. ~<! O

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The turbine generator was removed from service at 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br />, at Oa %, C, which time approximately 211 gallens of boric acid from the boric acid tank i t ..' ' y had been added to the reactor coclant system. 7tearn from the steam '

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generators ccntinuea to be supplied to the turbine plant for turbine gland y. A;j-

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8304150121 710217 d PDR ADOCK 05000244 5 S PDR 9

ROCHESTER GM .HO ELECTRtc CCRP. SHEET NO.

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.The control room operators were then instructed to maintain a reactor power level corresponding to a current of 10-7 amperes on the -

intermediate range channel and that it would be necessary to remove both reactor coolant pumps from service at the time of adding packing to the J pressurizer spray valve.

The Shift Foreman told the Head Control Operator that work on - -

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the pressurizer spray valves would not start immediately, that one of the pumps should be left running and that dilution should be started.

1144 gallons of dilution water were added prior to the shutdown of the 4 second reactor ecolant pump. -

One reactor coolant pump was shut down at 2355 hours0.0273 days <br />0.654 hours <br />0.00389 weeks <br />8.960775e-4 months <br />. Subsequently, -

the control room received a call from the containment requesting permission to start work. This would require the shutdown of the one remaining reactor coolant pump. The Head Control Operator shut down the second reactor  ?

coolant pump at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on July 6,1970.

The Shift Foreman ordered the two licensed control room operators .c to monitor the in-core thermocouples, as well as the reactor power level, -

while the pumps were out. He then proceeded into the planttoinspect its status and became occupied in operational duties and in extricating two auxiliary operators from a stalled elevator.

In the interval, the latching and tripping of the turbine stop valves during adjustment of the turbine trip pilot valve utilized steam from the r steam generators and resulted in lowering of the coolant temperature. The build-in of Xenon and the lowering of the coolant temperature required dilution to maintain the "D" bank of control rods between 140 and 180 steps out and to maintain constant power. Dilution was initiated at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and 1365 gallons of dilutien water were added while the reactor coolant pumps were shut down. In this same period, 25 gallons of boric acid were added -

to the volume control tank by the automatic make-up system. The control room operators were monitoring the in-core thermocouples and the reactor ,

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power level during this entire period, The Shift Foreman returned to the control room sometime after f (p -

0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> and realized that a violation of Technical Specification 3.1.1.la .

had occurred. The observed primary coolant temperature differential and the decreasing, but uniformly distributed, in-core thermocouple readings =

indicated that natural circulation was occurring. During this assessment, the control room was notified by a senior operator who had been assigned ...

to monitor the containment work that the work was completed and the con- E tainment was secured and locked. The Shift Foreman directed that a reactor coolant pump be put in service at 0222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br />. The intermediate range

channels were watched closely and no power change was observed. An 9

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ROCHESTER C A S AND ELCCTRIC CORP. $Nd w c July 15, 1970 3 O

ro.Dr. Peter A. MorrisO additional 2000 gallons of dilution water was added after the reactor coolant pump was started. The boron concentration of the primary coolant following this addition was 1039 ppm B.

The unit was returned to service at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />.

The Plant Operations Review Committee and the Nuclear Safety I

Audit and Review Board have not finalized their recommendations of appropriate action to be initiated to prevent recurrence of this violation i (Ref. Tech. Specs. Sec. 6.1. 4.1d6 and Sec. 6.1.1. 2d5). Pending such determination the following measures have been taken:

1. Orders have been issued that maintenance work is to be pez' formed only when duly authorized written procedures are available which coordinate the proposed maintenance work with plant operation during the maintenance activity.

2. Selected personnel representing the NSA&R Board, other than plant personnel, are being assigned to confirm that plant procedures are in compliance with Technical Specifications, and to audit non-routine plant operations for compliance. This will be the primary responsibility of such personnel during the period of this assignment.

(The Chairman of the Board and Chief Executive Officer and the President of Rochester Gas and Electric Corporation are Chairman and Vice Chairman respectively of the Nuclear Safety Audit and Review Board. )

3. A program has been instituted to have an outside organization re-evaluate operator proficiency.

4. A program has been instituted to have an outside organization assist a subcommittee of the NSA&R Board in a review of station operation, organization and procedures. f I.

Finalizing the recommendations for appropriate action to be initiated  ;

to prevent recurrence of Technical Specifications violations, and approval .'

and implementation of such recommendations are being expedited. We will .

promptly notify you of the action taken.

Very truly yours, [ ,

I Y ne0 K. W. Amish Vice PresJdent, Electric and Steam 't E on

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