ML20235P341
| ML20235P341 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/13/1987 |
| From: | Preston B Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87133, NUDOCS 8707200455 | |
| Download: ML20235P341 (3) | |
Text
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Pubhc Service Electric and Gas Company P O Box 236 Hancocks Bndge, New Jersey 08038 i
Nuclear Depadment JUL 131987 NLR-N87133 1
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL INFORMATION - REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby provides supplemental information in support of the request for amendment submitted on November 21, 1986 regarding containment vent / purge valve operation.
Attached is a revised page 3 of Enclosure 2 to the referenced letter which was previously transmitted in a letter dated December 18, 1986, but inadvertently omitted from additional submittals dated March 19 and May 15, 1987.
This transmittal does not affect the determination that the requested amendment does not involve a significant hazards consideration (ref: Enclosure 3 of the November 21, 1987 subrittal) since the attached change has already been provided.
If you should have any questions, please do not hesitate to contact us.
S'
- cerely, os.
Bruce A. Pbeston Manager - Licensing & Regulation Attachment 8707200455 870713 g
PDR ADOCK 00000354 gSq P
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'l The Energy People 9sewwm,
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l JUL 131987 Document Control Desk 2
C Mr.
G.
W. Rivenbark USNRC Licensing Project Manager Mr. R.
W.
Borchardt USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr.
D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 1
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ENCLOSURE 2 mixing in the FRVS inlet ductwork, this will result in relative humidity at the FRVS filters of less than the design conditions.
Our evaluation also included the radiological dose assessment due to the LOCA mass blowdown through the CPCS duct blow-out panels.
Assuming that the releases are unfiltered from the drywell to the environment during the 5 second purge valve closure time, with the coolant concentrations based on a pre-existing iodine spike equal to the short term technical specification limit of 4 uCi/gm, it is estimated that the resultant thyroid dose at the j
site boundary is 0.30 Rem.
The control room thyroid dose is estimated to be 3.5 X 10-4 Rem.
These doses are well below the 10CFR100 and GDC19 dose criteria. summarizes this calculation.
Furthe rmore, this assessment recognizes that the top of active fuel is not uncovered until approximately 25 seconds after the DBA LOCA (See HCGS FSAR Figure 6.3-20).
In order to minimize the probability that a LOCA could occur while the purge valves are open, a limit of 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> /365 days for combined purging, inerting, and CPCS operation is included in the proposed Technical Specification revision.
Pressure control using the 2-inch bypass flowpath is not included in the 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> /365 days limit.
Because HCGS utilizes a unique atmosphere recirculating Contai nme n t Prepurge Cleanup System (CPCS) to maintain offsite doses ALARA in lieu of purging through charcoal filters, an i
operational limit of 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> /365 days for the vent / purge valves l
is necessary to allow HCGS operational flexibility similar to plants with 90-100 hours /365 days limitations.
Analyses based on CPCS flow rate, CPCS filter efficiency and drywell volume have determined that the CPCS will reduce the initial drywell equilibrium radiciodine concentration to a new, lower equilibrium concentration in approximately four hours.
Any additional CPCS operation will not significantly lower the containment atmosphere radiciodine concentrations while in operational conditions 1, 2,
and 3.
These analyses also show that operation of the CPCS in through the torus and out through the drywell does not reduce the time required for CPCS operation.
In addition, PSE&G's discussions with the NRC regarding consideration of CPCS operation in this mode indicated that PSE&G had discovered only one Mark I BWR plant that operated this way (be suse it was their plant specific preference), and that the Hope C aek Operations staff prefers not to operate the CPCS in this m,de for reasons which include equipment considerations.
PSE&G :oncludes that operation of the Hope Creek CPCS will be in com711ance with BTP CSB 6-4 as presented in this submittal.
Had Hope Creek been designed without the benefit of a CPCS system, a 90-100 hour limit would permit about six inert /deinert cycles per year.
The additional four hours per deinert cycle for CPCd operation requires an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the purge valves open.
This results in a limit of 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.