ML20040B474
| ML20040B474 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/20/1982 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JPN-82-12, NUDOCS 8201260086 | |
| Download: ML20040B474 (4) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK 1
10 CoLUMeus CIRCLE N EW YOR K. N. Y.10019 (212) 397 6200 GEORGET BLRRY 7
OPE R ATING OF F IC E m TRUSTEES JOHN W. BOSTON JOHN S DYSON e
RE IDE PROCEDURES
&PEnropMANCE GEORGE L INGALLS j
JOSEPH R. SCHMIEDER WIC E C Mal A M AN E. DE
& MIEF NICHARD M FLYNN Ro err i MiLLONu LEROY W SINCLAIR January 20, 1982
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F R E DERIC K R CLARK JPN-82-12
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l THOM AS R FREY j
Director of Nuclear Rcactor Regulation l'f,'UlE'. 'C"'?.1'"'
U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
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' -N Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 2
's A Division of Licensing
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Subject:
James A. FitzPatrick Nuclear Power Pla'nt l'"
I Docket No. 50-333 Core Spray Line Replacement
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References:
1.
NRC letter, T.
A.
Ippolito to G.
T.
Berry (PASNY), dated August 25, 1981 2.
James A.
FitzPatrick Nuclear Power Plant In-service Inspection Program for Welds and Sup-ports
Dear Sir:
As a result of ultrasonic examinations conducted at the Fitz-Patrick Plant, the Power Authority detected an indication in a weld in a core spray line.
To correct this condition, the line was replaced from the reactor pressure vessel safe end out to the first isolation valve.
This work was completed during the Reload 4/ Cycle 5 refueling outage currently in progress.
Reference 1 states that the Power Authority must comply with the FitzPatrick Inservice Inspection (ISI) Program (Referes:ce 2).
I In the ISI Program, the Power Authority committed to test repaired and replaced components in accordance with ASME Section XI 1974 Edition and the 1975 Summer Addenda, in conjunction with requests for relief from other provisions of the Code.
This edition of the Code specifies that the replaced section of the core spray line be hydrostatically tested.
Since this section of the line can-not be isolated from the reactor pressu.e vessel, verbatim compliance with References 1 and 2 would subject 'che reactor vessel to the hydrostatic test.
The Power Authority considers unnecessary hydrostatic tests O
of the reactor vessel highly undesireable.
This is due to the stresses on the vessel and the fact that it is only designed for
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four hydrostatic tests over the life of the plant.
Therefore, 8201260096 820120 4
PDR ADOCK 05000333 P
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the Authority is revising the FitzPatrick ISI Program to specify testing of repaired or replaced components in accordance with the 1977 Edition of Section XI and Addenda through the Summer of 1978.
This is the latest edition approved by 10 CFR 50.55a for use in ISI programs. contains the revisions to the FitzPatrick ISI Program.
The 1977 Edition of the Code specified in the revisions would allow system leakage tests in lieu of hydrostatic tests.
For the replaced core spray line, the system leakage test will be conducted at a test pressure equivalent to the nominal opera-ting pressure associated with 100% reactor power.
The test tem-perature will comply with the pressurization temperature limits specified in the FitzPatrick Technical Specifications.
The Power Authority considers the use of the 1977 Edition of the Code adequate to assure the reliability of repaired and replaced components.
This has also been discussed with your staff and found acceptable to them.
The Power Authority is implementing the revisions to the FitzPatrick ISI Program immediately.
This is necessary to pre-vent a delay in returning the FitzPatrick plant to service on schedule.
If you have any questions, please do not hesitate to contact us.
Very truly yours, b
I
['J. P. Bayne'11 ~
i Senior Vice President Nuclear Generation s
.o 1.3.8 Repair Provisions Because of the vintage of the James A. FitzPatrick Nuclear Power Plant, not all systems and components were originally designed and fabriceted to the ASt!E Boiler and Pressure Vessel Code.
Systems and components re-classified herein in accordance with the inservice inspection requirements of 10 CFR 50, 50.2(v), 50.55a(g) and Regulatory Guide 1.26 as ASME Class 1, 2 and 3 chall be examined in accordance with this program.
Consequently, relief is requested from the requirements of Articles IUA-4000 of ASME Section XI Repair Procedures and the subsequent Articles IWB-4000, IWC-4000, and IWD-4000.
Ir. lieu of these requirements in order to assure quality and integrity of the repaired and/or replacement component, the following shall be accomplished:
1.3.8.1 Codes and Standards Repairs on the components of the systems classified in the inservice inspection program as ASME Class 1, 2, and 3, shall be made in accordance with:
the Code or Standard used for the original fabrication; or, ASME Section XI, 1977 Edition and all Addenda through the Summer of 1978.
1.3.8.2 Quality Assurance All work pertaining to repairs and replacements sball be performed in accordance with the requirements of the existing James A.
FitzPatrick Quality Assurance Program.
1.3.8.3 Pressure Test After repairs by welding on the pressure retaining boundary of components (except repairs on cladding), a pressure test shall be performed in accordance with the provisions of IWA-5000, 1977 Edition and all Addenda through the Summer of 1978.
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Appendix B.
includes:
descriptive information and definitions of (1) Code Exemptions, (2) Relief Requests, and (3) Weld Summary Sheet Terms; a Weld Summary Sheet Index (listing of systems inc]oded in the Program); and Held Summary Sheets for each system.
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l Appendix C.
represents the color-coded Inservice Diagrams I
(ISD's) which define the ASME Class 1, Class 2, and Class 3 boundaries for those systems listed in Appendix B.
The inspection program for ASME Class 3 systems and components is covered in Section 1.3.7 of this report.
1.2 Technical Approach l
In general, the inservice inspection requirements in the 1974 Edition through the Summer 1975 Addenda which are applicable to ASME Class 1 components and systems are considered to be sufficient and workable to provide a reasonable and prudent level of inspection that will help to ensure the pressure boundary integrity of essential systems of a boiling water reactor plant.
However, the Code requirements applicable to ASME Class 2 components and systems are considered in many cases to need enhancement.
The ASME has recognized various aspects that need improvement in the 1974 Edition through the Summer 1975 Addenda and has subsequently made many improvements in its later Editions and Addenda.
These later Editions and Addenda (e.g.,
1977 Edition, Summer 1978 Addenda) are recognized by 10 CFR 50, and are directly referenced in the Inservice Inspection Program.
The Inservice Inspection Program Update was prepared to the degree practicable in accordance with the Code requirements.
Where the Code requirements were determined to be either incomplete or impracticable, specific requests for relief from Code requirements are identified.
Each request for relief has been evaluated and an alternative examination is specified.
In 9
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