ML19325E943

Application for Amend to License DPR-72,consisting of Rev 1 to Tech Spec Change Request 170 Re Pressure/Temp Limits Rept

ML19325E943
Person / Time
Site:	Crystal River
Issue date:	10/31/1989
From:	Boldt G FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19325E944	List: ML19325E943 ML19325E947 ML19325E949
References
3F1089-22, NUDOCS 8911130081
Download: ML19325E943 (6)

Text

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coneonation October 31, 1989 3F1089-22 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72  :

Technical Specification Change Request No. 170 Rov, i  !

Pressure / Temperature Limits Report  ;

Der ~ Sir {

Florida Power Corporation (FPC) hereby submits Technical  !

Specification Change Request No. 170 Revision 1, requesting -

amendment to Appendix A of Operating License No. DPR-72. Proposed i replacement pages for Appendix A and associated bases, which were l inadvertently ommitted from the original change request packet, are '

provided.

l This revision is provided to reflect the proposed use of 15 effective full power years (EFPY) Reactor Coolant System pressure / i temperature limit curves for Crystal River Unit 3. The 15 EFPY  ;

pressure / temperature limit curves supersede the 8 EFPY curves  !

provided in the sample Pressure / Temperature Limits Report and are i provided for informational purposes only. l Sincerely,

)

Gary Boldt, Vice President Nuclear Production j GLB/BPW Attachment 4 l

xct Regional Administrator, Region II Senior Resident Inspector f l 8911130081 891031 4 00{1 PDR ADOCK 05000302 i PDC P

' UhNhHAL OFFICE: 3201 Thirty fourth Street South

• P.o. flox 14042 . St. Petersburg, Florida

• 33733}g \ (8 A Florida Progress Company

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... l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER )

) DOCKET NO. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE Gary Boldt deposes and says that the following has been served on the Designated State Representative and Chief Executive of Citrus County, Florida, by deposit in the Unitod States mail, addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Department of Health and Citrus County Courthouse Rehabilatative Services Inverness, FL 32650 1323 Winewood Blvd.

Tallahassee, FL 32301 A copy of Technical Specification Change Request No. 170, Revision 1, requesting Amendment to Appendix A of Operating License No. DPR-72.

FLORIDA POWER CORPORATION Gary B61dt, Vice President Nuclear Production SWORN TO AND SUBSCRIBED BEFORE ME THIS 31ST DAY OF OCTOBER 1989.

h jotary Public Notary Public, State of Florida at Large My Commission Expires fo / / o/ /9 9 ND14Y PUBLIC. STATE OF FLORfDA Af LAR0f Vy COMuts$10N [xPlRES 001,19.1992 c.owtoinove.nAnnto=Aoucysc

STATE OF PLORIDA COUNTY OF CITRUS Gary Boldt states that he is the Vice President, Nuclear Production for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

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cary holdt, Vice President Nuclear Production Subscribed and sworn to me, a Notary Public in and for the State and County above named, this 31st day of October, 1989.

hotary Public Notary Public, State of Florida at Large My Commission Expires Ip llgl9 k I

h3f MY NBec. STATE OF rt0Al0A At tJJG Mt GWi.t%'DN tvi4[!, OCL 4,1992 ',

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.. , i FLORIDR POWER CORPORATION  !

CRYSTRL RIVER UNIT 3 [

DOCKET NO. 50-302/LICENSB NO. DPR-72 i REQUEST NO. 170, REVISION 1  !

PRESSURE /TEMPERRTURE LIMITS REPORT l

LICENSE DOCUMENT INVOLVED: Technical Specifications l PORTIONS: Index, Page la Definitions, Page 1-8 .

3.4.9.1 $

I 4.4.9.1.1 Figure 3.4-2  !

Figure 3.4-3 i Figure 3.4-4 6.9.1.7 [

DESCRIPTION OF REQUEST:

This submittal requests that reactor vessel fluence-dependent ,

pressure and temperature limits be removed from Technical '

Specifications (TS) and relocated to a Pressure / Temperature Limits Report. The term, PRESSURE / TEMPERATURE LIMITS REPORT, will be  :

added to the Definitions Section of TS. A new administrative ,

reporting requirement will be added to existing reporting i requirements of TS. The individual specification and applicabla .

Bases will be revised to state that the values of reactor vessel l pressure /temperaure parameters shall be maintained within the .

limits identified in the Pressure / Temperature Limits Report.  !

RERSON FOR REQUEST >

l Technical Specifications (TS) address pressure and temperature  !

limits associated with parameters that generally change with reactor vessel fluence requiring the processing of changes to TS -

to update these limits each fuel cycle. These limits are developed using an NRC-approved methodology, therefore, the license amendment  !

process is an unnecessary burden on the licensee and the NRC. An alternative to including the values of these reactor vessel fluence-dependent parameters in individual specifications is responsive to industry and NRC efforts on improvements in TS and is provided in this change request.  ;

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4 g EVALUATION OF REQUE8it It is essential to safety that the plant is operated within the bounds of pressure / temperature limits and that a requirement to maintain the plant within the appropriate bounds must be retained in the TS. However, the specific values of these limits may be modified by licensees, without affecting nuclear safety, provided that these changes are determined using an NRC-approved methodology and consistent with all applicable limits (e.g., heatup limits, cooldown limits, inservice leak and hydrostatic testing limits).

A pressure / Temperature Limits Report will be submitted to NRC with the values of these limits. This will allow continued trending of this information, even though prior NRC approval of the changes to these limits would not be required. The Pressure / Temperature Limits Report will documer.t the specific values of parameter limits resulting from the licensee's calculations including any revisions to such parameter values. The methodology for determining pressure / temperature limits is documented in NRC-approved Topical Report BAW-10046A, Rev. 2, " Methods of Compliance With Fracture Toughness and Operational Requirements of 10CFR 50, Appendix G",

June 1986. As a consequence, the NRC review of proposed changes to TS for these limits is primarily limited to confirmation that the updated limits are calculated using an NRC-approved methodology and consistent with all applicable limits of the safety analysis.

The pressure / temperature limits calculated in accordance with the approved' methodology will be included in a report, Pressure / Temperature Limits Report, and provided to the NRC upon issuance as required by the proposed Technical Specification 6.9.1.7. Controlled copies of the Pressure / Temperature Limits Report will be maintained at Crystal River Unit-3 (CR-3) and will be revised as required by the future CR-3 reactor vessel fluence periods. Attachment 1 provides a sample copy of a 15 EFPY l Pressure / Temperature Limits Report for information purposes only.

.,, e' SNOLLY EVALUATION OF REQUEST: j Florida Power Corporation (FPC) proposes the removal of pressure / l temperature limits from Technical Specifications does not involve l a significant hazard consideration. The removal of the fluence  ;

dependent variables from Technical Specifications has no impact '

upon plant operation or safety. The Technical Specification will ,

continue to require operation within the pressurc/ temperature i limits for each cycle reload calculated by the approved reload design methodology. Appropriato actions to be taken if limits are violated will also remain in Technical Specifications.  !

FPC concludes this change will not:  !

1. Involve a significant increase in the probability or consequence of an accident previously evaluated because the ,

removal of pressure / temperature limits from the Crystal River i Unit 3 (CR-3) Technical Specifications has no influence or impact on the probability of a Design Basis Accident (DBA) 1 occurrence.

The cycle specific pressure / temperature limits will be relocated to a PRESSURE / TEMPERATURE LIMITS REPORT. The requirements to operate CR-3 within the limits will continue to be maintained in Technical Specifications.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated because the removal of the fluence dependent variables has no influence, impact, nor does it contribute to the probability cr consequences of an accident. The fluence dependent variables are calculated using an NRC approved methodology, and Technical Specifications will continue to require the operation within the pressure / temperature limits.

3. Involve a significant reduction in the margin of safety because the margin of safety presently provided by current Technical Specifications remains unchanged. This proposed amendment still requires operation within the pressure /

temperature limits as obtained from the NRC approved methodology, and appropriate actions to be taken when, or if ,

limits are violated, remain unchanged.