ML19344D212

Tech Spec Change Request 81 Incorporating New Max Average Planar Linear Heat Generation Rate Curve to Sections 2.1.a.1,3.10 & 4.10 of App A.Certificate of Svc Encl

ML19344D212
Person / Time
Site:	Oyster Creek
Issue date:	03/04/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19344D209	List: ML19344D208 ML19344D212 ML19344D214 ML19344D216
References
NUDOCS 8003110545
Download: ML19344D212 (7)

Text

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to ti.; Cyster Crcek i!ucleer Genercting Staticn Sparcting License cr. nges t.c in:cr;crzte a nu naPLt.'3i, curve to 9.cticns 2.1.'.. ) , 3.10. and 4.10 of 'pperr.'ix

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CLLi'IFICUL CF SLINICL

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ting St.iticn Opc rtir.g Liccnce .,cc fil?d with hc United Stetcc huc1ccr Dcgula tcry Commicsion on

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Tae I:onorable Henry Von Spreckclscn Scyor of Lt.cc-y Totinthip P. C. Sox 475 Fcr wi niver,!!cw Jerscy J:2SEY CL'.; TEAL PC..LR & LIGlil' CCliP1NY By ' &, a -j V1cc Proc JEn CATLL: March 4, 1980 4

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Enclosed ic cne copy of Technicc1 Spccificction Cnenge Fzcuest I:o. El for tne Cyctor Crec< .:uclerr Gcnercting station Optr: ting License.

Tnis cecumcnt w:s filed witr. tne United 5tstcs I:uclecr Eegulctory Comiccion cn March 4, 1980.

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JERSEY CENTRAL P0h'ER & LIGHT CO'IPANY

, OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE DPR-16 (DOCKET NO. 50-219) 1 Applicant requests the Commission to change Appendix A to the above-captioned license as follows :

1. Sections to be Changed:

Sections 2.1.A.1, 3.10, and 4.10 s

2. Extent of Changes (1)'Section 2.1.A.1; Delete descriptions of fuel types 11 and IIIE.

(2) Section 3.10.A; Modify and add descriptions of figures; Figure 3.10-1 (MAPLHCR Limits for five loop operation)

Figure 3.10-2 (MAPLGHR Limits for four loop operation)

Figure 3.10-3 (!!APLHCR multiplier)

(3) Section 3.10.B; Delete LHGRd and P/P for fuel types II and IIIE.

(4) Section 3.10.C; Make it applicable to fuel type IIIF for four loop operation only.

Delete B values for fuel types I, II, IIIE, V and VB (5) Section 3.10 Basis, Page 3.10-4, paragraphs 2 and 3 Switch order of paragraphs appearing.

Modify and add descriptions of Figures 3.10-1, 3.10-2, and 3.10-3.

(6) Section 3.10 Basis, page 3.10-5, paragraphs 3 and 4; Delete references to fuel types 11 and IIIE for pellet-clad thermal conductance and power spike penalty. Paragraph 3 is added to paragraph 2.

(7) Section 3.10 Basis, Page 3.10-6, paragraph 1; Make this paragraph applicable to fuel type IIIF for four loop.

operation only.

(8) Page 3.10-9, Figure 3.10-1; Replace Figure 3.10-1 and add figures 3.10-2 and 3.10-3.

-(9) Section 4.10.C; bbke this section applicable to fuel type IIIF for four loop oper-ation only. -

(10) Section 4.10 BASIS, Page 4.10-2; Address MAPLHGR limits in the event of a single pump trip.

3. Changes Requested:

See Attachment I ]

1 4 Discussion This Technical Specification Change Request is submitted as a demonstra-tion of continued compliance with the requirements of 10CFR50.46. This request returns the MAPLHGR limits of all fuel types (IIIF, V and VB) to those specified in Amendment No. 33 (1) and extends the limits for type V and VB fuel to 40 GWD/MTM. The ECCS Evaluation Models used for the above changes are the same models used to calculate MAPLHCR limits of Amendment No. 33 (2). The model application to Oyster Creek including the MAPLHGR limits calculation is presented in reference (3). This request also . includes a set of MAPLHGR limits of all fuel types (IIIF, V and VB) for four recirculation pump operation. The ECCS Evaluation Models used for fuel types V and VB are the same models used to calculate MAPLHGR ,

limits for five pump operation (2) and the MAPLHGR limits for fuel type IIIF are those of the current technical specification. LOCA analyses for the four pump operation are presented in reference 5.

Due to the unavailability of critical replacement parts, one recirculation pump was removed from service and the plant operation continued under more restrictive limits adapted (6, 7) and specified in the Amendment No.

35 (8), and modified by Amendnent No. 39 (9). In our letters of April 30, 1979 (6) and May 24, 1979 (7), we stated that the Oyster Creek Station would continue to operate within the more restrictive limits until such time that the analyses were completed to justify operation at higher limits, or a fifth recirculation pump was restored to service. This proposed technical specification will enable Oyster Creek to operate with five or four recirculation pumps in service.

This request also returns the MAPLHGR multiplier to the technical speci-fications as approved by Amendment No. 33 (1). The MAPLHGR multiplier is made applicable to all fuel types for five and four loop operation, even though MAPLHGR limits of fuel type IIIF f or four loop operation were not based on ENC NJP-BWR ECCS-EM (2). This is an additional conservetism imposed on fuel type IIIF for four loop operation.

Assembly Averaged Power Void Relationship (AAPVR) is made applicable to fuel type IIIF for four loop operation only. MAPLHGR limits of fuel types IIIF, V and VB for five loop operation and fuel types V and VB for four loop operation are based on ENC NJP-BWR ECCS-EM (2). This model does not require input from a blowdown analysis of the plant by GE ECCS-EH (5). Therefore, AAPVR is no longer applicable to fuel types IIIF, V and VB for five loop operation and fuel types V and VB for four loop operation.

This request further deletes references to fuel types I, II, IIIE for peaking f actors in Section 2.1.A.1, local LHGR in Section 3.10.B. and pellet-clad thermal conductance and power spike penalty in the Section 3.10.B basis._ These fuel assemblies are no longer in the core and are not ex-pected to be reinserted. Therefore, these references are no longer applicable.

Discussion (continued)

The delav time of isolation condenser initiation from reactor low low water level was changed from 10 to 3 seconds by Amendment No. 39(9) . The event times are reported in references 2 and 4 for five and four loop, respectively. LOCA analyses indicate a 10 second delay. Calculatiors have not been performed that specifically vary isolation condenser delay time; however, several calculations have been performed in which isolation condenser capability was varied. They include. calculations (1) no isolation condenser, (2) one isolation condenser operating, with:

(3) both isolation condenser operating. Results of the above calculations are reported in reference 2. In all cases where isolation condenser capability s was modeled, the PCT was decreased, because of a slight increase in the rate of system depressuri:ation; therefore the effect of only an additional 7 seconds of isolation condenser injection is expected to be small.

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4 REFERENCES

1. NRC (D.L. Ziemann) Letter to JCP&L (I. R. Finfrock). Amendment No. 33 to Provisional Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station, dated November 11, 1978.

2. XN-75-55-(A), XN-75-55, Supplement 1-(A), E9-75-55 Supplement 2-(A),

Revision 2, April 1977. Exxon Nuclear Company WREM-Based NJP-BWR ECCS Evaluation Model and Application to the Oyster Creek plant.

3. XN-NF-77-55, Revision I, March 1978. Oyster Creek LOCA Analyses Using the ENC NJP-BWR ECCS Evaluation Model.

4. XN-NF-79-78, January 1980.

LOCA-ECCS Analyses Supporting Four-Pump Operation of Oyster Creek Reactor.

5. JCP&L Letter to NRC. Oyster Creek Nuclear Generating Station, Loss-of-Coolant Accident Analysis Reevaluation and Technical Specification Change Request No. 42, Attachment 1, dated December 23, 1975.

6. JCP&L (I. R. Finfrock) Letter to NRC (Director, Nuclear Reactor Regulation). Four Loop Operation, dated April 30, 1979.

7. JCP&L (I. R. Finfrock) Letter to NRC (Director, Nuclear Reactor .

Regulation). Request for Amendment to Provisional Operating License No. DPR-16. Technical Specification Change Request No. 73, dated May 24, 1979.

8. NRC (D. L. Ziemann) Letter to JCP&L (I. R. Finfrock). Amendment No. 35 to Provisional Operating License No. DPR-16 for Ovster Creek Nuclear Generating Station dated Iby 30, 1979.

9. NRC (D. L. Ziemann) Letter to JCP&L (I. R. Finfrock). Amendment No. 39 to Provisional Operating License No. DPR-16 for Oyster Creek Nuclear Generating Station, dated July 23, 1979.

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