ML20137N549
| ML20137N549 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/27/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 8602030285 | |
| Download: ML20137N549 (6) | |
Text
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o, UNITED STATES P '
o NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555
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January 27, 1986 Docket No. 50-219 Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
0YSTER CREEK CONTAINMENT PURGE AND VENT VALVE REPLACEMENT CANCELLATION - REQUEST FOR ADDITIONAL INFORMATION Re:
Oyster Creek Nuclear Generating Station In a letter dated September 24, 1985, you proposed to cancel your commitment to replace the large containment purge and vent valves in the Cycle 11 Refueling (Cycle 11R) outage. The staff is reviewing your request and finds that it needs additional information to complete its review. Questions detailing this needed information are enclosed and must be responded to before the review can continue.
You are requested to provide the additional information by March 7,1986, so that the staff may complete its evaluation before the comencement of the Cycle 11R outage. A copy of the enclosed questions was sent to M. Laggart of GPU Nuclear (GPUN) and discussed by telephone with him and other GPUN personnel on January 15, 1986. An acceptable alternative to providing this information by the above date and to your comitment for the valve replacement is to propose a technical specification requiring the containment purge and vent valves to be closed whenever the reactor is in the power operation and hot shutdown modes. To meet your comitment, the technical specifications must be effective before restart from the Cycle 11R outage. An acceptable technical specification is provided in Enclosure 2.
8602030285 060127 DR ADOCK 05000239 PDR
Mr. P. B. Fiedler :. January 27, 1986 The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, gginal sisned bf!
John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing
Enclosures:
1.
Request for Additional Information 2.
Technical Specification cc w/ enclosure:
See next page DISTRIBUTION Docket RBernero CJamerson NRC PDR OELD ACRS (10)
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Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station cc:
G. F. Trowbridge, Esquire Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1800 M Street, N.W.
Post Office Box 445 Washington, D.C.
20036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Comissioner Bishop, Liberman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Commission Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628
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BWR Licensing Manager GPU Nuclear 100 Interpace Parkway Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, N w Jersey 08731 D. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station i
Post Office Box 388 Forked River, New Jersey 08731 l
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 CONTAINMENT PURGE AND VENT VALVE REPLACEMENT CANCELLATION 1.0 Historical Background i
The licensee has been maintaining the purge and vent valves mechanically re-stricted from opening more than 30' in accordance with NRC's interim position as stated in the October 23, 1979 NRC letter. GPU committed to replace all containment purge and vent valves with qualified valves rather than qualifying the existing valves in their letter of July 31, 1980. A subsequent letter from CPU dated August 27, 1981 requested an extension in the schedule for re-placing the containment purge and vent valves f rom December 1.1981 to the end of their cycle 10 reload refueling / maintenance outage. The licensee's April 19, 1984 submittal included a report number 4-01-82 by the Clow corporation containing operability demonstration information for the Clow replacement valves. This information was reviewed and found to demonstrate operability for the Clow valves from the 90* full open position under LOCA conditions in the proposed installation configuration (BNL TER dated July 26, 1984). The licensee's September 24, 1985 submittal proposes cancelling the replacement of
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the existing valves with Clow valves and contains an analysis (TDR 266, Revi-sion 1) that is intended to demonstrate valve operability for the existing valves under combined seismic and DBA/LOCA conditions from a restricted valve opening angle of 30' open.
2.0 Preliminary Evaluation The existing valves are shown in the table below:
Valve size Number (Inches)
Location Manufacturer Use V27-1 18 Outside containment Centerline Drywell vent V27-2 18 Outside containment Centerline Drywell vent V27-3 18 Outside containment Rockwell Drywell purge V27-4 18 Outside containment Centerline Drywell purge V23-13 8
Outside containment Continental Drywell purge V23-14 8
Outside containment Fisher Drywell purge V23-15 8
Outside containment Continental Torus purge V23-16 8
Outside containment Fisher Torus purge V28-17 12 Outside containment Fisher Torus vent Outside containment Fisher Torun vent V28-18 12 The analysis included in the September 24, 1985 submittal from CPU (Technical Data Report TDR Number 266 Revision 1, dated May 9,1985) has been examined and does not contain sufficient information for a complete review of operabil-icy demonstration under the postulated accident conditions for the presently installed valves.
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2 The items listed below are intended as a guide for completing the information required to perform a valve operability review in order to comply with NUREG-0737 Item I.1.E.4.2.4.
Dynamic Torque Coef ficients (CT). The license-tates on page 5 of TDR 266, Revision 1, that the torque coefficientr m ed in his analysis may be obtained f rom the valve manufacturers and rs.. snees a letter. This is in-adequate for a review. Acceptable documentation in this area should in-clude test reports that detail how the torque coefficients were determined including a description of the test setup, test disc size and shapo, aspect ratio, flow conditions, media used, etc., so that confidence can be estab-lished in the torque coefficients used in predicting valve dynamie loads.
Valve Installation Configuration. The licensee's analysis TDR 266 Revi-sion 1 does not provide this information for each valve. Typically, the following information is required:
1.
Direction of flow.
2.
Disc closure direction.
3.
Curved side of disc, upstream or downstream (anymmetric discs).
4.
Orientation and distance of elbows, tees, bends, etc. within 5 pipe diameters of valve.
5.
Shaft orientation.
6.
Distance between valves.
Dynamic Torque Analysis. The licensee provides in TDR 266, Revision I the methodology used for,his torque analysis and references Oyster Creek Purge and Vent Valve Analysis Calculation Book Calculation 1302 SX-322C-A07. The referenced calculations, which should include assumptions used should be provided for the reviewer.
Actuator Torque Margin.
In order to demonstrate adequate torque margin by comparing valve torque loads during closure to actuator closure torque availability, curves or incremental data, such as spring torque at various valve angles need to provided by the licensee.
_ Seismic Qualification of Valves. The licensee has not indicated by rei-erencing documentation that the valve assemblies are seismically qualified.
As an example, for further guidance in understanding the type of infornation requirad for operability demonstration, the licensee should exanine the Clow
" Purge and Vent Valve Operability Qualification Analysis Report" Number 4 82 submitted to the NRC with the CPU letter of April 19, 1984 In addition, Attachment A to the November 29, 1982 NRC letter (V. Noonan to D. Crutchficid) can be used as a guide for valve operability demonstration requireoents.
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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT PURGE SYSTEM (Optional *)
4 LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge supply and exhaust isolation valves shall be closed.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2 and 3 ACTION:
With a drywell or suppression chamber purge supply and/or exhaust isolation valve open, close the open valve (s) within one hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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~~._-t SURVEILLANCE REQUIREMENTS l
4.6.1.8 The drywell or suppression chamber purge supply and exhaust isolation valves shall be verified to be closed at least once per 31 days.
' *This specification may be modified if the facility design conforms to Branch Technical Position CSB (6-4) of the Standard Review Plan.
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GE-STS 3/4 6-11a
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