View source for 3F0385-18, Forwards Addl Request for Relief from ASME Section XI Inservice Insp Requirements for Emergency Feedwater Piping Between Steam Generators & First Valves Upstream That Provide Isolation.Response Requested by 850601

{{Adams
| number = ML20112F115
| issue date = 03/22/1985
| title = Forwards Addl Request for Relief from ASME Section XI Inservice Insp Requirements for Emergency Feedwater Piping Between Steam Generators & First Valves Upstream That Provide Isolation.Response Requested by 850601
| author name = Westafer G
| author affiliation = FLORIDA POWER CORP.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F0385-18, 3F385-18, NUDOCS 8503270399
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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Florida l       power CCRPOR ATION I               March 22,1985 3F0385-18 f
L Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20535

==Subject:==
Crystal River Unit 3                                                                                                                                                        j Docket No. 50-302                                                                                                                                                           l Operating License No. DPR-72 ASME Section XI, Relief Requests

==Reference:==
Letter dated April 8,1982 from 3.F. Stolz, NRC, to
: 3. A. Hancock, FPC

==Dear Mr. Denton:==

The referenced letter granted relief from compliance with the ASME Boiler and Pressure Vessel Code, Section XI, Article IWC-3000, for hydrostatic testing of piping in the feedwater and main steam line between the first isolation valve for the steam generator and the turbine main stop valve. During preparations for the upcoming outage, it is determined that similar relief was required for a portion of the emergency feedwater system that is not isolatable from the steam generator.
Transmitted herewith is the additional request for relief from Section XI. Since the receipt of your approval will be a condition for startup from the 1985 refueling outage, we request that your response be issued as soon as possible but not later than June 1,1985.
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GENERAL OFFICE 3201 Thirty-fourth Street South.P.O. Box 14042, St. Petersburg, Florida 33733 813-866 5151

March 22,1985 3F0385-18 Page 2 Florida Power Corporation has enclosed, per 10 CFR 170, an application fee (check
         #722296) of one hundred fifty dollars ($150.00).
Sincerely, o
G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management DGG/jel Attachments cc:    Dr. 3. N. Grace Regional Administrator, Region II U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement 101 Marietta St., N.W., Suite 2900 Atlanta, GA 30323 Alden 3. LaMoy District Authorized Nuclear Inspector Supervisor Factory Mutual Engineering 12 Perimeter Center East, N.W., Suite 1200 Atlanta, GA 30346

m FLORIDA POWER CORPORATION INSERVICE INSPECTION RELIEF REQUEST #210                                              i Reference Code: ASME Boller and Pressure Vessel Code, Section XI, 1980 Edition through Winter 1981 Addenda I.'  Components for which exemption is requested:
Emergency feedwater piping between the steam generators and the first valves upstream that provide positive isolation.
II.   . Reference Code Requirement that has been determined to be impractical:
Article 5000 of Code Section IWC, System Hydrostatic Testing,1980 Edition through Winter 1981 Addenda.
III. Basis for Requesting Relief:
Modifications to the emergency feedwater system are currently planned for the upcoming refueling outage. The modifications include the addition of a flange to the auxiliary feedwater header to allow for steam generator cleaning and an NRC mandated upgrade to the emergency feedwater system.                   Hydrostatic testing the emergency feedwater line after modifications would be impractical since it would involve pressurization of the steam side of the steam generators. Filling this section of piping with water could overstress the pipe and associated supports making this procedure highly undesirable to perform.
IV. Alternate Examination:
All emergency feedwater system welds which cannot be hydrostatically tested will be subjected to magnetic particle testing and radiographic examinations.
V. Implementation Schedule:
The alternate examinations described above will be completed prior to the end of the upcoming refueling outage.
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