ML20032B717
| ML20032B717 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/21/1981 |
| From: | James Shea Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8111060197 | |
| Download: ML20032B717 (3) | |
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October 21, 1981 MllLY[f Docket No. 50-245
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- mm muna 12 MEMORANDUM FOR:
Dennis M. Crutchfield, Chief w
Operating Reactors Branch f5, DL
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'FROM:
James J. Shea Project Manager h[Yh s
Operating Reactors Branch #5, DL
SUBJECT:
FORTHCOMING MEETING WITH NORTHEAST NUCLEAR ENERGY COMPANY (NNECO) TO REVIEW DESIGN CHANGES RESULTING
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FROM MILLSTONE 1 ISOLATION CONDENSER STEAM INLET PIPING WATER llAMER Date:& Time:
Tuesday November 3,1981 Location:
Millstone 1 site, East Lyne Connecticut
Purpose:
To review:
o isolation condenser steam inlet piping water hamer incidents o plant and operating procedure changes that have evolved to prevent recurrance
Participants:
NRC Glainas, WHodges, ASerbiz, RFrahm, JShea and J. T. Shedlosky NNE_C0 PBlasioli, WRomberg, EDeBarba, and George Corneius, et al.
Original signed by James J. Shea, Project Manager Operating Reactors Branch f5 Division of Licensing 8
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October 21, 1981 Cocket No. 50-5 f-
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Dennis. M. C"utchfield, Chief
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FROM:
J%es J. Shea, Project Manager /
Opehting Reactors Branch #5,'DL
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SU3 JECT:
FORTHC0gINGMEETINGWITHNORTHEASTNUCLEARENERGY COMPANY {LSTONE1ISOLATIONCONDENSERSTEAM NNECO) TO REVIEW DESIGN CHANGES RESULTING FROM MIL PIPING WATEp HAMMER g' y
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Date:
Tuesday f' s November 3,193{,.
MillstoneIsite,'Igt Location:
East'Lyrejonnecti
Purpose:
To resie[
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oisoltioncondensersItaminletpipingwaterhammer
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'inc'idents
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o,jlant and operating procedure changes that have
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Participants:
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Glainas; WHooges, ASerbiz. RFrahbii JShea and J. T. Shedlosky h
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PBlasioli, WRomberg, EDeBarba, and Geogge Corneius, et al.
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James J.
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Operating Reactors Branchi #5 Division of Licensing i
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We have reviewed your responses to our' questions relating to the Millstone 1.-
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1071981 water ammer event and plan to meet with NNEC0 representatives August I
in early November 1981 to discuss tie following:
1.
Basis for new feedwater controller
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2.
Displacement uf anchor bolts, you believe, resulted from slippage in the d-concrete slab due to relaxation of the pr21oad.
Explcin relaxation mechanistically.
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Amplify your reqpons elative to axial piping stresses, minimal stress concentrations and fa iguc effects at reinforcing pads.
4.
Discuss the expected consequences if i
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e Mai. ' steam isolation had occurred concident with scran, from 100% power o Main steam isolation had occurred or would have occurred after automatic turbine trip
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and explain the basis for operator trip procedures following reactor scram (any inprovements from previous water hammer events).
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5.
There are four reported isolation condenser piping water hammer events, _
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February 12, 1976, March 1978, December 19, 1979 and August 10, 1981.
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h Please compere the event sequences i
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Provide assurance that an undetected iso-condenser pipe crack would not result in pipe failure during water hammer conditions.
7.
Discuss the tests completed to assure that UT devices perform satisfactorily on the scram discharge volume header.
8.
How was isolation condenser pip _ing integrity confirmed following the water hammer event? ('u4 uw A prWcd
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9.
Provide Figures 7 and 8 referenced in yo'u[ earl'ier' answer to Question 8.
10.
Discuss the response expected for August 10, 1981 transient if the feedwater pump trip had been installed.
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