3F0390-23, 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  |
| 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) | |
Text
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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., " 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. is the non-proprietary revision to B&W Nuclear Services i
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 y
POST OFFICE DOX 219
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
{
l, 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
[
Limiting Material l
Identification WF-70 Atypical l
(Heat No.)
-6
-6 Init 1,RTNDT 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.