ML20151T755

Amend 106 to License DPR-61,revising Tech Spec 4.12, High Energy Piping Sys, Expanding Augmented Inservice Insp Program to Include Weld Locations on Steam Lines to Auxiliary Feedwater Pumps

ML20151T755
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/09/1988
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151T752	List: ML20151T751 ML20151T755 ML20151T764
References
NUDOCS 8808170245
Download: ML20151T755 (9)

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. 'o,, UNITED STATES I g NUCLEAR REGULATORY COMMISSION 3 8 WASHING TON. D. C. 206S4

\.....J CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NEC,K, PLAN _T AMENDMENT TO FACILITY OPERATING LICENSE Amenenent No.106 License No. DPR-61

1. The Nuclear Regulatory Comission (the Conrnission) has found that:

A. The application for amendirent by Connecticut Yankee Atomic Power (thelicensee),datedMarch9.1987conplieswiththestandardsand requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Consnission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Consnission; C. There is reasonable assurance (1) that the activit'es authorized by this anendnent can be conducted without endangering the health and safety of the pubitc, and (ii) that such activities will be conductt.1 in compliance with the Comission's regulations; C. The issuance of this arendnent will not be inimical to the conson defense and security or to the health and safety of the public; and E. The issuance of this arendrent is in accordance with 10 CFR .' art 51 of the Comission's regulations and all applicable requirements have been satisfied.

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7. Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachnent to this license anendnent, and paragraph ?.C.(2) of Facility Operating License No. CFR-61 is hereby arended to read as folicws:

(2) ,T,e,ch,1,ca,1, Sg,c,1,fi ca ti on s The Technical Specificattor.s contained in Appendix A. as revised ,

thrcugh Anendrent No.106, are hereby incorporated in the license.

The liter.see shall operate the facility in accordance with the Technical Specifications.  ;

3. This license amendnent is effective as of the date of issuance. ,

F0 THE h0 CLEAR REGULATORY CCPPISSION ,

,. j / Y ,

Jch T. Stolz. Director .

Fr ect Directorate I-4 '

O visicn of Reactor Projects I/II Office of Nuclear Reactor Regulation Attachnent:

Changes to the Technical l Specificaticos .

I Cate of Issuarce: August 9. 1988 l

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l ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE NO. OPR-61 DOCKET NO. 50-213 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the i

area of change.

1 REMOVE INSERT 4-24 4-24 4-25 4-25

--- Table 4.12-2 page 1

-- Table 4.12-2 page 2

-- Table 4.12-2 page 3

.-- Table 4.12-2 page 4 4

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4 4.12 High Energy Piping System i

Augmented Inservice Inspection Applicability: App!!es to inservice testing of certain main steam,  !

feedwater, and steam supply to auxiliary feedwater  !

system piping welds, identified in Tables 4.12-1 and -

4.12-2.

Objective: To provide assurance of the continued integrity of the main steam, feedwater, and auxillary feedwater systems over the plant's service lifetime.

Specification: A. The augmented inservice inspection program at each weld identified in Tables 4.12-1 and 4.12-2 shall be performed as follows in accordance with the applicable l requirements of the ASME Section XI Code, specified in

• Specification 4.10.  !

(1) First Ten-Year Inspection Program a) Nondestructive examination of each weld identified in Tables 4.12-1 and 4.12-2 for the }

first three consecutive 3-1/3 year inspections.

These inspections may be adjusted to coincide with the scheduled regular ASME Section XI lospections.

b) A monthly visual examination for evidence of leakage of areas identified in Tables 4.12-1 and  !

4.12-2.

(2) Successive Inservice Inspection Programs a) If no indications are detected or the indications  !

do not exceed the allowable standards of the ASME Section XI Code during inspections ,

specified in 4.12.A.l.a. subsequent inspections will be limited to once during each 10-year ,

inspectiore interval.

b) If indications are detected that exceed the allowable standards of the ASME Section XI Code, they shall be investigated and evaluated  !

and the frequency of examination for that weld '

shall revert to Specification 4.12.A.I.a.

c) Consistent with paragraph 4.12.A.2.a. visual examinations of areas identified in Tables 4.12-1 and 4.12-2 will be performed semiannually, j 4-24 Amendment No. If, 106

(3) Repairs, Re-examination, and Tests Repairs, re-examination, and piping pressure tests shall be conducted in accordance with ASME Section XI.

Basist Consistent with the guidance contained in NRC Mechanical Engineering Branch Technical Position No. 4, dated March 18,1975, an Inservice inspection program is institutec at potential high energy pipe break locations at which consequences of a postulated pipe rupture "could" affect the plant's safe shutdown capability and other methods of pipe restraint are considered to be impractical. This augmented inrpection program will provide a means for timely detection of cracks propagating in the piping. Since the Haddam Neck Plant was built prior to adoption of the ASME Code for ISI, there is not cornplete accessibility for inspection in accordance with specific requirements of that code.

inspections will be conducted to the extent practical within the limitations of design, geometry, and materials of the components. Visualinspections will be conducted for all areas identified in Tables 4.12-1 and 4.12-2.

References:

1. CYAPCO Specla! Report "High Energy Pipe Break Outside Containment," dated February 5,1975, as supplemented on March 13,1975, April 4,1975, and May 1,1975.

2. E. J. Mroczka letter to C.1. Grimes, dated December 5, 1986,

Subject:

Environmental Qualification of Equipment Outside Containment and High Energy 1.ine Breaks.

3. F. J. Miraglia letter to E. J. Mroczka, dated January 27, 1987,

Subject:

Augmented Inservice Inspection and Resolution of Environmental Qualification and High Energy Line Break issues.

4 25 Anend:nent No. I6,106

Page 1 TNME 4.12.2 .

MEID EDCATIGES G8 STEMt SUPPLY LINES 10 AUKILIAmr PEIDem!R FWWS tocation Description Size (inches) Method of Inspection 1 Pipe to Valve MS-lev-38 3" Volumetric, Surface and Visual 2 Pipe to seducer 3" Voltametric, Surface and Visual 3 Pipe to Pipe 3" Volumetric, Surface and Visual 4 Stub-in 2-1/2" - SA-601-2 2 1/2"" Voltametric, Surface and Visual 5 Pipe to Valve MS-NRV-48 3" Volumetric, Surface and Visual 6 Stub-in 3" - SDHV-601-4 3" Voltametric, Surface and Visual 7 Pipe to Elbow 4" Voltametric, Surface and Visual 8 Pipe to Elbow 4" Voltametric, Surface and Visual 9 Pipe to Elbow 4" Voltmetric, Surface and Visual 10 Elbow to Reducer 4* Voltametric, Surface and Visual 11 Reducer to Pipe 3" Voltmetric, Surface and Visual 12 Pipe to Pipe 3" Voltametric, Surface and Visual 13 Pipe to Elbow 3' Voltmetric, Surface and Visual 14 Pipe to Elbow 3" voltametric, Surface and Visual

, 15 Pipe to Pipe 3" voltametric, Surface and Visual a

@ 16 Pipe to Pipe 3" Voltametric, Surface and Visual 5

17 Pipe to Valve MS-CV-1304 3" Voltametric, Surface and Visual

• 18 Valve MS-CV-130V to Pipe 3* Voltametric, Surface and Visual g 19 Pipe to Valve 3" Voltametric, Surface and Visual

Page 2 17eu!: 4.12.2 .

De!!D IDCEFIONS Of S1DWI SUPPLY LINES 10 JMILIARY FEEDem!R MBTS Iocation Description Size (inches) nethod of Inspection 20 Valve to Pipe 3" Voltametric, Surface and Visual 21 Pipe to Elbow 3" Voltametric, Surface and Visual 22 Elbow to Pipe 3" volumetric, Surface and Visual 23 Pipe to Elbow 3" Volumetric, Surface and Visual 24 Elbow to Pipe 3" Volumetric, Surface and visual 25 Pipe to Tee 3" Voltametric, Surface ated Visual 26 Tee to Valve MSV-1201A 3* Voltametric, Surface and Visual 27 Tee to Pipe 3" Voltametric, Surface and Visual 28 Pipe to Flange 3" Surface and Visual 29 Valve MS-NRV-18 to Pipe 3" Volumetric, Surface and Visual 30 Pipe to End-Cap 4" Volumetric, Surface and Visual 31 Stub-in 4" SDHV-601-1 3" Volumetric, Surface and visual 32 Pipe to tipe 4" Volumetric, Surface and Visual 33 Valve MS-retV-28 to Pipe 3" Volumetric, Surface and Visual 34 Stub-in 4" SDHV-601-1 4" Voltametric, Surface and Visual f 35 Pipe to Elbow 4" Volumetric, Surface and Visual 36 Elbow to Pipe 4" Volumetric, Surface and Visual o

37 Pipe to Pipe 4" Voltametric, Surface and Visual N

38 Pipe to Pipe 4" Voltametric, Surface and Visual 5

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1NKE 4.12.2 *

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MED IDOtFIGE5 G8 STENE SFPLY LDES TO ME[ILIARY FEIE55tfER PGr5

! Location Description Size (inches) Flethod of Inspection l 39 Pipe to Tee (B.W.) 4" Voltanetric, Surface and Visual -

40 B. w. h to Valve Pts-V-1302 4" Volumetric, Surface'and Visual 41 B. w. Tee to 3" SA-601-28 3" Volumetric, Surface and Visual 42 valve 7tS-V-1302 to Pipe 4" Voltametric, Surface and Visual 43 Pipe to Pipe 4a Volumetric, Surface and Visual

. 44 Pipe to Elbow 4" Volumetric, Surface and Visual 45 Elbc.w to Pipe 4" Volumetric, Surface and Visual 4

l 46 Pipe to meducer 4" Voltametric, Surface u d visual l 47 meducer to Valve Pts-V-1201A 3" Surface and Visual l

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Page 4 TABLE 4.12-2 BREAK LOCATIONS ON STEAM SUPPLY LINES TO AUXILIARY FEEDWATER PUMPS Number Location Description of Welds Size Method of Inspection 31 Pipe to Elbow Welds 2 4" Volumetric, Surface and Visual 32 Pipe to Elbow Welds 2 4" Volumetric, Surface and Visual 33 Pipe to Reducer Welds 2 3"/4" Volumetric, Surface and Visual 34 Pipe to Elbow Welds 2 3" Volumetric, Surface and Visual 35 Pipe to Elbow Welds 2 3" Volumetric, Surface and Visual 5

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