ML19308D742
| ML19308D742 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/21/1978 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19308D743 | List: |
| References | |
| NUDOCS 8003120908 | |
| Download: ML19308D742 (4) | |
Text
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-e REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIDUTION FOR INCOMING MATERIAL 50-302 REC:
ORG: STEWART W P DOCDATE: 07/21/78 NRC FL PWR DATE RCVD: 07/24/79 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 40 FORWARDING LIC NO DPR-72 APPL FOR AMEND: APPENDIX A TECH SPEC PROPOSED CHANGE NOS 31 & 32 CONCERNING REMOVAL OF THE ORIFICE ROD ASSEMDLIES FROM UNIT 3 AND MEW LIMITING CCNDITION FOR OPERATION CONCERNING AXIAL PWR SHAPING ROD GROUP.. NOTARIZED 07/25/7G PLANT NAME: CRYSTAL RIVER M3 REVIEWER INITIAL:
XJM DISTRIBUTOR INITI AL: p
- +**** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIEUTION CODE AOO1)
FOR ACTION:
BR CHIEF ORB 44 BC**W/7 ENCL
_MT INTERNAL:
(REG,f;ILC44W/ ENCL NRC PDR**W/ ENCL T & E+*W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CORE PERFORMANCE ER**W/ ENCL AD FOR SYS & PROJ nW/ ENCL ENGINEERING ER**W/ ENCL REACTOR SAFETY BR**W/ ENCL FLANT SYSTEMS GR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL; LPDR'S CRYSTAL RIVER, FL**W/ ENCL TERA **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL
$$$$$$$$$33$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$
CHECK NER: 284,588 AMOUNT:
$4.000.00 0
CHECK AND COPY OF TRANSMITTAL LTR ADVANCED TO W.
MILLER (LFMB) (07/25/78) UPON RECIEPT
$0$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$
DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NER:
7023<svvy g
SIZE: 3P+1P+1SP oG*********************************
THE END 8003120 90 8
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h,p' OSO'ofaff ERATORY DOCIET R.E C0?Y W. P. STEWART. DlR ECTOR f
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July 21, 1978 Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 5UBJECT: Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Sir:
Enclosed are three (3) originals and forty (40) copies of Technical Speci-fication Change Requests No. 31 and 32 requesting amendment to Appedix A of Operating License No. DPR-72.
As part of this request, proposed re-placement pages for Appendix A are enclosed.
Technical Specification Change Request No. 31 addresses the removal of the Orifice Rod Assemblies (ORA's) f rom Crystal River Unit No. 3.
This change request is supported by Revision 1 to the Babcock & Wilcox report BAW-1490, Licensing Considerations for Continued Cycle 1 Operation Without Burnable Poisca Rod Assemblies and Orifice Rod Assemblies, which was submitted under l
separate cover on this date.
On June 6, 1978, Florida Power Corporation (FPC) submitted Technical Specification Change Request No. 29, which ad-dressed removal of the Burnable Poison Rod Assemblies (BPRA's) f rom the CR
- 3 reactor. Change Request No. 29 was supported by the Babcock & Wilcox report BAW-1490, Licensing Considerations for continued Cycle 1 Operation Without Burnable Poison Rod Assemblies. The changes requested to the CR #3 Technical Specifications in Request No. 29 are still applicable and should be acted upon by the NRC. However, the supporting document for these changes is now Revision 1 to BAW-1490 instead of the original BAW-1490 report. Both Change Request No. 29 and 31 are related to the same safety issue (recent anomalous mechanical behavior of the BPRA/ ORA latching mechanism) and are supported by Revision 1 to BAW-1490.
FPC considers Amendment Requests No. 29 and 31 to be a class III amendment per 10 CFR 170.22 as they involve the same single safety issue. Therefore, the licensing fee, in the amount of four thousand dollars ($4,000), submitted on June 6,1978, should be applied to Change Request No. 29 and 31.
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General Office 3201 TNrty-fourtn Street Soutn. P.O. Box 14042 St. Petersburg, Flor.da 33733 e 813-866-5151
Director.
Page Two July 21, 1978 Office of Nuclear Reactor-Regulation Technical Specification Change. Request No. 32 involves a new Limiting Condition for Opera ion (LCO) concerning the Axial Power Shaping Rod Group as a result of the. replacement of four fuel assemblies at CR #3.
This change' request is also supported by Revision 1 to the Babcock & Wilcox report BAW-1490 but involves a different safety issue.
FPC considers Change Request No. 32 to be a Class III amendment per 10 CFR 170.22 as it involves a single safety issue. Enclosed is FPC's licensing fee, in the amount of four thousand dollars ($4,000), for Change Request No. 32.
Also enclosed is one signed copy of Certificate of Service for Technical Specification Change Requests No. 31 and 32 to the Chief Executive of Citrus County, Florida.
Very truly yours, FLORIDA POWER CORPO TION 0
W.P. Stewart WPS/QBD/ emf cc: Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta,-GA 30303 File: 3-0-3-a-3 l
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n UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF
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FLORIDA POWER CORPORATION
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DOCKET No. 50-302 CERTIFICATE OF SERVICE W.P. Stewart deposes and says that the following has been served on the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:
Chairman, Board of County Commissioners of Citrus County, Citrus County Courthouse, Inverness, FL 32650 An original copy of Technical Specification Change Requests No. 31 and 32 requesting amendment to Appendix A of Operating License No. DPR-72.
FLORIDA POWER CORPORATION
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W.P. Stewart Director, Power Production SWORN TO AND SUBSCRIBED BEFORE ME THIS 21st DAY OF JULY,1978.
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Notary Public j
Notary Public State of Florida at Large My Commission Expires: July 25, 1980 (NOTARIAL SEAL)
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