ML19210B645
| ML19210B645 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 09/14/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Arnold R METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19210B646 | List: |
| References | |
| RTR-REGGD-01.083, RTR-REGGD-1.083 NUDOCS 7911110115 | |
| Download: ML19210B645 (5) | |
Text
s' D**D
- D k 1 k oo o
September 14, 1976 DISTRIBUTION:
L. M / g4Q $
NRC PDR Cocket No. 50-289 YRne&Mdb TJCarter 0 ELD Metronolitan Edison Conpany 01&E(5)
ATTH: Itr. R. C. Arnold RReid Vice President - Generation GZwetzig j
P. O. Box 542 iFairtile i
Peading, Pennsylvania 19603 RIngram DEisenhut Gentlenen:
TBAbernathy e
n 3,E: T!!REE MILE ISLAND UNIT No.1 General Design criteria (GOC) 30 and 32 of Appenb N to 10 CFR Part 50 require that cont,ents that are part of the reactor coolant pressure boundary receive per. odic inspection and testing of critical areas to assess their structural and leaktight integrity. The steam generator tubes constitute over 50% of the area of the total primary systen i
pressure-retaining boundary in pressurized water reactors. Our letter dated October 17, 1974, requested you to propose suitable technical specifications for the surveillance of the steam generator tubes consistent with the recuirements of the GDC and Regulatory Guide 1.33 titled " Inservice In-scection of Pressurized Water Reactor Steam Generator Tubes."
In your re-sponse dated Novenber 29,1974, you 1isted reasons why you believed the stean generators at THI-1 should not be subject to these reauirenents.
As noted belcw, however, we conclude that tnere is, as yet, insufficient lono tern operating experience with the B&W once-through steaa gen?rators to justify not perfortling these inspections. Therefore, you are reouested to submit a proposed amendment to your technical specifications consistent with the enclosed nodal technical soe':ifications @ich are based on Revision 1 of R.G.1.83, dated July 1975.
Both the original and revised R.G.1.83 refer to a tube pluggina limit and plunging criteria, but neither provides ouidance on how these are to be cuantified. The plugging linit in the enclosed model technical specifi-cations is based on the minimum tuce wall t'11ckness needed to maintain tuoe integrity during a LOCA combined with a safe shutdown earthquake and an or'erational allowance to account for time intervals between inspections.
We have concluded that plugging linits that are based en these con ~ * ' rations satisfy the recuirenents of the GDC and are acceptable to us.
Stean cenerator tu' e leakar:e can be an indication of tube c'emdation; there-c fore, we have concluded that a leakace lit 11t and a li9iting ci'ndition for eneration should be included in the technical soecifications ta ensure tinolv action in the event of steam generator tube decradation. A l W uce limit such as the one in the erciosed model technical specificatio:
s accovaole to us.
1586 001 9L g9 f
1 110// S
/
, C.
D**D
- D
}
!!etropolitan Edison Company.cc o
3 Certain types of stean generators have completed the first cycle of op-eration with tube inspection results that have indicated little discern-ible degradation. These early-in-life inspection results may not be indicative of the total 40 year design life of stean generator tubes in terms of tube integrity. Therefore, we have concluded that sur-veillance of steam generator tube integrity should be covered b. technical specifications for all facilities including those where early inspection cycles have not indicated any discernible or increasing degradation.
i The enclosed model technical specifications gives credit for favorable i
early inspection results by extending subsequent inspection intervals and keeping at a minimum the number of tubes to be probed.
We request that within 45 days of receipt of this letter, ynu revise or resubait your reouest for a license amendment using the enclosed model technical specifications for guidance. The model technical specifications should be appropriately adapted to your specific fomat and to the number of steam generators in your plant.
Sincerely, W!'Rhv Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Model Technical Specifications
~
cc w/ enclosure:
See next page 1586 002
.0RB&D09 nnR#4?n0R C.-0
..:g0R._
orr.c *
.G.J$eNi[Iina mea.irl.ile R..._ eid ev
. 9L6.L2.6 91[&ll6 h! Y 9/ 8776 a r.
- Foran MC.318 (Rev. P.53) MCM 0240 W u. s. oovenmusur emenvene orricss se74.sas.tes
. ~.:.
4 Petronolitan Edison Company cc:
G. F. Trowbridae, Eso.
Shaw, Pittman, Potts, & Trownridge 1800 !! Street, H. W.
Washington, D. C.
20036 GPU Service Corporation Richard W. Heward, Project flanager Thomas !!. Crimnins, Jr., Safety and Licensing Manager 260 Cherry Hill Road Parsippany, llew Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Sroad Street Johnstown, Pennsylvania 15907 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonberry Township 2148 Foxiana Road Middletown, Pennsylvania 17057 i
Miss ifary V. Southard, Chairnan Citizens for a Safe Environment P. O. Box 405
!!arrisburg, Pennsylvania 17108 i
Government Publications Section State Library of Pennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17126 1586 003
'oPPic E W suRNAuRW D' ATE b Forma AEC418 (Rev. SS)) AECM 0240 W u. s. oOvERNMENT PRINTING OPPICEB 9974 828-9SS
Metropalitan Edison Company cc:
G. F. Trowbridge, Esq.
Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 GPU Service Corporation Richa' d W. Heware, Project Manager r
Thomas M. Crimmins, Jr., Safety and Licensing Manager 260 Chcrry Hill Road Parsippany, New Jersey 07054 Pennsylvania Electric Company Mr. R. W. Conrad Vice President, Generation 1001 Broad Stree:
..Johnstown, Pennsylvania 15907 Mr. Weldon B. Arehart, Chairman Board of Supervisors of Londonderry Township 2148 Foxiana Road Middletown, Pennsylvania 17057 Miss Mary V. Southard, Chairman Citizens for a Safe Envircrment P. O. Box 405 Harrisburg, Pennsylvar.ia 17108 Government Publications Section
~
State Library of Dennsylvania Box 1601 (Education Building)
Harrisburg, Pennsylvania 17125
~
1586 004
9 s
NOV031975 DEFINITIONS 2
The following definition should be added to Section 1.0, DEFINITIONS, of facility technical specifications to complement tne Fire Protection Program:
" FIRE SUPPRESSION WATER SYSTEM:
A FIRE SUPPRESSION WATER SYSTEM shall consist of:a water source (s);
gravity tank (s) or pump (s); and distribution piping with associated sectionalizing control or isolation valves.
Such valves include yard hydrant curb valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser."
1586 005