ML20012F294

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Forwards Nonproprietary Rev to 51-1176431-02, Crystal River 3 Reactor Vessel...Temp Overpressure Protection, in Support of Tech Spec Change Request 174,Suppl 1 Re Response to Generic Ltr 88-11
ML20012F294
Person / Time
Site: Crystal River Duke energy icon.png
Issue date: 03/30/1990
From: Boldt G
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012F295 List:
References
3F0390-23, 3F390-23, GL-88-11, NUDOCS 9004110090
Download: ML20012F294 (3)


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{ee e,I C ORP O H At ION March 30, 1990 3F0390-23 U.S. Nuclear Regulatory Commission

  • Attention: Document Control Desk -

Washington, D.C. 20555  ;

Subject:

Crystal River Unit 3 i Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request 174, Supplement 1 Supplement to Generic Letter 88-11 Response

Dear Sir:

Florida Power Corporation (FPC) hereby submits the attached supplemental information related to the NRC review of FPC's Generic Letter 88-11 response. Attachment 1, " Analysis Assumptions Used to Prepare the Crystal l River 3 15 EFPY Pressure / Temperature Limit Curves" is the information requested by members of your staff during our March 9,1990 teleconference.

i Attachment 2 is the non-proprietary revision to B&W Nuclear Services Document 51-1176431 " Crystal River 3 Reactor Vessel Low Temperature l Overpressure Protection." A proprietary version of this document, as well cs the proprietary application and affidavit, was submitted to the NRC as part of Technical Specification Change Request No. 174. However, FPC did j not submit the accompanying non-proprietary version of the document at that time. This submittal fulfills the 10CFR2.790 requirement to provide, to the extent possible, a non-proprietary revision of the information for public disclosure.

i 9004110o90 900330 "'

f,'DR ADOCK 05000302 PDC POST OFFICE DOX 219

  • CRYSTAL RIVER, FLORIDA 32629-0219 * (904) 563 2943 y

A Florida Progress Company

March 30, 1990 3F0390-23 Page Two should you have any questions or require further information, pleat.e contact this office.

Sincesoly, Gary Boldt Vice President Nuclear Production PMB:BPW Attachments xc Regional Administrator, Region II Senior Resident Inspector I

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l Attachment 1, FPC Letter to NRC, Dated March. 30, 1990 l

l HAnalysis Assumptions Used to Prepare Crystal River 3 15 EFPY Pressure / Temperature Limit Curves" T/4 Location 3T/4 Location

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! Limiting Material l Identification WF-70 Atypical l (Heat No.)

Init 1 ,RT NDT -6 -6 l

Adjusted RTNDT at 15 ,EFPY 203 171

( F)

Copper / Nickel Content 0.35/ 0.59 0.41/ 0.10 (weight percent) l 1) B&W Nuclear Services Document BAW-2049 " Analysis of Capsule l CR3-F Florida Power Corporation Crystal River Unit 3," dated September 1988, submitted FPC to NRC on October 20, 1988 in accordance with 10CFR50 Appendix H.

2) B&W Nuclear Services Document BAW-2091 " Pressure / Temperature Limits for 15 EFPY For Crystal River Unit 3 Nuclear Plant,"

dated August 1989.