ML20099L467
| ML20099L467 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/09/1984 |
| From: | Martin T Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-84-03, IEB-84-3, NUDOCS 8412010139 | |
| Download: ML20099L467 (3) | |
Text
{{#Wiki_filter:50-35% hmes J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/4304316 Vica President ' Engineering and Construction i i November 9, 1984 L Dr. Thomas E. Murley, Adminis tra tor U.S. Nuclear Regulatory Commission l Of fice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Dr. Murley:
NRC IE BULLETIN 84-03 DATED AUGUST 24, 1984 REFUELING CAVITY WATER SEAL i HOPE CREEK GENERATING STATION l l This Bulletin describes an incident in which the pneumatic ref ueling cavity water seal in a PWR plant failed and I i rapidly drained the refueling cavity. The refueling cavity water seal at Hope Creek Generating Station is quite dif ferent from that described in this f Bulletin. At Hope Creek Generating Station the seal is a permanently installed assembly consisting of an annular steel bulkhead plato connected to the RPV flange with a flexible metal bellow. The outside diameter of the bulkhead L plate is welded to the drywell wall. Because Hope Creek Generating Station has a free-standing steel containment, there is a similar flexible stool bellow connecting the bulkhead plate to the refueling cavity wall. Both bellow assemblies are protected by stool guard rings. Any leakage through either bellows assembly will be collected and drained through a line with a leak detection alarm. The seal assembly has no active components. All heavy loads passing over the ref ueling cavity, seal while the cavity is flooded are carried by a single failure proof handling system. We can postulate no mechanism for a gross seal failure. Mako-up to the refueling cavity is automatically supplied from the condensate transfer system without opera-tor action. Wo estimate that the available mako-up flow will exceed 150 gpm. Thorofore, we can see no credible seal f ailure which would significantly reduce the water level in the refueling cavity or the connected spent f uel pool. There is no credible mechanirm to postulato a seal failuro ,n.
0-Dr. Thomas E. Murley 2 11/9/84 having any ef fect on fuel in transfer or stored in the spent fuel pool. No operator action is required to prevent clad-ding damage. It should be noted that it is imposs ible for t the removal of water from the refueling cavity to uncover the spent f uel racks. Nevertheless, an abnormal operating procedu re " Decreasing Level in the Refueling Canal or Spent Fuel Pool" will be prepared by April 1, 1985, to cover the eventuality of a refueling cavity soal failuro. 4 Should any further information be desired, we would be pleased to discuss it with you. i Very truly yours, 1 i i -{ i i C U.S. Nuclear Regulatory Commission l Document Control Desk Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Of fice of Inspection and Enforcement 1 Division of Roactor Construction Inspection Wash ing ton, D.C. 20555 i i NRC Hosident Inspector - Hopo Crook P.O. Box 241 Hancocks Bridge, Now Jersey 08038 i C i i DEOS 1/2
7 o STATE OF NEW JERSEY )
- SS.
COUNTY OF ESSEX ) AFFIDAVIT THOMAS J. MARTIN, of full age, being duly cworn upon his oath deposes and says: 1. I am the Vice President - Engineering and Construction for Public Service Electric and Gas Company. 2. I have read the attached response to NRC IE Bulletin 84-03 and the facts stated herein are true and correct to the best of my knowledge, information and belief. 2nd M Jj A1 V ' Thomas . ~ Mar' tin Sworn to and subsgribed to before me this 4#\\ day of IV000.m be r,198 4. G.Ah v\\ - d i_ u MARCARET A. HARyty fl01ARY PUBUC Of Nlw Jtnsti N Comm:ues bpwei Apd 4,iggs i L .}}