ML20086L738

Telecopy AO 74-8:on 740306,portions of Reactor Vessel Shell Temp Decayed to Less than 185F While Reactor Pressure Remained Above 250 Psig.Caused by Personnel Error. Instructions Will Be Issued to Personnel

ML20086L738
Person / Time
Site:	Peach Bottom
Issue date:	03/08/1974
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086L737	List: ML20086L732 ML20086L738
References
AO-74-8, NUDOCS 8402080489
Download: ML20086L738 (3)

Text

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- Mr. Jame.s P. O'Reilly, Director . .

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United States Ator.ic Energy Co=:icolon , ,

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' Directorate of_ Regulatory Operations, . .G ' '

631 Park Avenuo , , , .

King of Prunnia, Penncylvania ,19406

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Subject:

Abnorm 1 Occurrence 24-Hour Notification .'" .

Confirrir.5 zy conversation with Mr. R. A. Teil. A.I.C. Region 1 Regulatory Operations Office on March 8, 1974.

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5eference: Licenae Nucher DPR-44,... Acendeent Number.1 ,

Technical Sp'ocification Reference 3 6.A.2 -

Report No.: 50- 8 - '

Report Date: 3/8M  ! . .

occurrence Date: 3/6M4 .-

Facility: Peach Bottom Atomic Power Station - Unit 2 it. D.1, Delta, Pennsylvania 17314 .

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Identification of occurrence: .

.  ; .F911owihg a cain etcar. !ine.icolation .te=ti pertion' of s the . reset-or. "-.^ ,

x w asel 'rAnil te=peracures decayed'to less thsn 185'T while reacter r.. . ."..

pre'scure remdined ab6ve 250'psig.' '.Chis excee'ds' a' lis:iting'cenditfn " ' '

. . for operation as stated in Technical Specification paracrsph 3.6.A.h

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Conditions Prior to Occurrence: - t- 4 " ' " '

. Reactor chutdown following a =ain steam. isolation'tcat.which resulted .

.ih trippi~gt o't toth recirculation pu=ps.- Reactor water cleanup system arid' rdactor core isolation system in'.scrvice.

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Description of Occurrence: ..

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Following a start-up test which isolated the main steam linea with .

the plant at a no=inal 25% power, reactor conditions were stabilized with both recirrulation pu .pa out of service and the control rod drive p.u:ps out of cervice. 'Ihe reactor water clean-up system was in

, service on full recirculation. Reactor vessel level was r.aintained by

. the' reactor core isolation epoling system. .This system also esintained reactor vessel pressure essentially constant at approximately 40') poig by takir.c a s=all flow from the upper part of the vessel. With the reactor pressure and level stabilized in this ennner, the cold

,' water being delivered to the reactor veegel' cooled the lower portion of the vessel shell to approximstely 125 F. This condition exceeds. .

the liciting condition for operation which states * "The reactor vessel I

I shall not be prescurized above 250 paig unlearx the reactor vessel terperatures are equal to or greater than 185"F if ' fuel is in the reactor.vescel " - '

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Designation of Apparent Cause of Occurrence.

The main stec= icolation start-up tect recults in ir=ediate clocure of all asain steam isolation valves which in turn .cause a reactor scram.

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) - With the locs of steam to the Turbine / Generator, the Turbine / Generator

)' must be tripped which in turn counca fact trancter of the auxiliary

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busces and tripping of both recirculation pumps. All plant systema operated in accordance with design during this start-up tect. The

-" sain etens isolation test was followed i==ediately by another start-up I l

i test which de=onstrates the ability to control reactor veccel level

' frc= outcide the Control Room. During this demonstration, operations p which cust be perforced from the Control Roo: necocisted with the k reactor eyatecs were delayed until the Shutdown From Outside The I @controlRoosEttrt-UpTestvaecocpleted. The delay in restarting ,

J i the recirculation purps following the icolation pereitted the vessel temperaturen to diverge to the point where the recirculation purps * '

could not be rectnrted without violating a Technical Specification.

Additionally, the reactor vecsel pressure vac not decreased below 250 paig when the vessel te:peratures decayed to 185 F. .

Analysis of Occurrence:

During this particular period, the upper portions of the reactor vessel, including the vessel flange, head flange, tenzioning studs and doce, retained above kCC F. The control rod drive purps were

.out of service such that cold water was, not being supplied to the control rod drive stub tubes. The nuclear steam cupplier has revie.ted the tecperature and preneure data and has advised that the conditionc vere within the design li=ito specified by Section 3 of the ASG code.

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Corrective Adion: .

Instructiena shall be incue'd to =ake an effort to return the recirculation p.tspc to service as soon as possible following any plant transientL If this cannot be accomplished, the reactor relief valves shall be utilized to depressuri::e the reactor to less than 250 psig before vessel chell tcrperatures can' decay to lecs than 185 F. It should be pointed out that the liciting conditions for operation vere excee:!ed ac a result of a planned start-up test and not during nor:al plant operationc. Norm l operating proceduren ensure that these liciting conditions for operation are not exceeded during norr.al plant operations. -

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dt? V. T. Ullrich, Superintendent '

Peach Bottom Ato:ic Fover Station. ,

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ro, Aic.u i nn. my i 4. iW) AI Ol 0240 We and retura For sleasture, X For leformaven, t o (s.m. ... . nit) imriats atuin s RO Chief, FS&EU PilILADELPIIIA' ELECTRIC CO.

RO:llQ (4)

RO:DL (4) DATE PB-2 A0 50-277-74-8 R0 Files Central Mail & Files T .m. .n o a.t>  :=rie atuaans The above A0 is forwarded for information.

Distribution will be made by this office to the PDR, Local PDR, NSIC, DTIE, and State TO (Nem. .na unit) thiftALs Rt= ARKS Representatives.

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• ' E. J. Brunner Region I '

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D rer no. ears ,.

8-337-1246 3/11/74

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