ML20198T212
| ML20198T212 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/04/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606110369 | |
| Download: ML20198T212 (3) | |
Text
_.
f DUKE POWER GOMPANY P.O. BOX 33180 CHAMLOTTE, N.C. 28242 IIAL H. TUCKER TELEPHONE r=g (704) ara-4 san l
June 4, 1986
(
Mr. Harold R. Denton, Director j
Office of Nuclear Reactor Regulation
)
U. S. Nuclear Regulatory Constission I
Washington, D. C.
20555 Attention:
Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4 Re:
Catawba Nuclear Station, Unit 1 Docket No. 50-413
Dear Mr. Denton:
My letter of June 3,1985 requested relief from the inservice inspection l
requirements of Section XI of the 1980 Edition of the ASME Boiler and Pressure l
Vessel Code (with addenda through Winter 1980). The request concerned inservice inspections of the Boron Recycle System at Catawba, Unit 1.
Attached is a revision to the basis for requesting relief which better describes the actions Duke has taken to ensure adequate testing and safe operation of the system. This is an amendment to a previous relief request, therefore the requirements of 10 CFR 170.21 are not applicable and no fee is required.
Very truly yours, l
Hal B. Tucker l
WLH: sib Attachment xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Dr. K. Jabbour Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC Resident Inspector Catawba Nuclear Station O
i 8606110369 860604 PDR ADOCK 05000413 O
4 Page i of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION - UNIT 1 REQUEST FOR RELIEF FROM ASME CODE SECTION XI (WITH ADDENDA THROUGH WINTER 1980)
Inservice Inspection Requirements 1.
Component For Which Exemption Is Requested:
(a)
Name and Number:
Two isolation valves on the INB, Boron Recycle System relief valve header discharge are being replaced because of over pressurization from a Unit
- 2 hydrostatic test.
Valve INB-378, Weld #1NB121-4, 3",
SS Valve INB-395, Weld #1NB172-5, 6",
SS (b)
Function:
This system channels discharged water from the relief valves to the Boron hold up tanks A or B.
Valves INB378 and INB395 isolate Unit I from Unit 2.
(c)
ASMI Section III Code Class:
Equivalent to ASME Class 3 (d)
Valve Category:
N/A l
2.
Reference Code Requirement That Has Been Determined To Be Impractical:
ASME B & PV Code,Section XI, 1980 through winter 1980 addenda. Article IWD-5000.
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page 2 og 2 R qu:st For R: lief From ASME Cods Ssetion XI (With Add:nds Through Wintsr 1981) i 3.
Basis For Requesting Relief:
Performing a hydrostatic test on the Boron Relief Valve discharge header would be impractical, extremely difficult and very costly due to the following reasons.
A Hydro Test would constitute isolating the Boron Hold-Up Tank (a) which would in turn require removal of the Reactor vessel head and defuelings.
Freeze sealing the three (3) inch and six (6) inch lines would (b) require cutting piping on the Unit 2 side of the isolation valves giving rise to the possibility of contaminating Unit 2 piping.
(c) The Operations Group has implemented controls to preclude closing isolation valves INB66 and INB84 at the same time. This will insure the discharge header has a continuous flow to hold up tank A or B which are vented to atmosphere.
4.
Alternate Examination:
A 1007. radiograph inspection (NDE-10) and an inservice leak test of Welds INB121-4, and INB172-5, will insure volumetric and operational intregrity.
These welds will also receive a Hydro inspection at the ten (10) year inspection interval.
5.
Implementation Schedule:
These examinations, with exception of the Hydrostatic Test, will be conducted after the valve installations are complete and prior to the system being declared operable.
5