ML20041F086

Responds to 811215 Request for Info Re Containment Venting & Purging.Proposed Tech Spec Changes Re Standby Gas Treatment Sys Will Be Submitted by 820415

ML20041F086
Person / Time
Site:	FitzPatrick
Issue date:	03/08/1982
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
JPN-82-28, NUDOCS 8203160176
Download: ML20041F086 (11)

Text

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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMaus CIRCLE N EW Yonx. N. Y.100* ^

l 212 i' 397 62o0 G E O",0,E,, ,T ,U,7c ,,,

oranavine orriCan JOHN W. BOSTON Co.a mesaw P DE T PaoCEDURES ePERFORMANCE GEORGE L. LNG ALLS vlC S CMaleMAN JOSEPH R. SCHMIEDER g 3ECuf 0VE VICE PAttlDENT & CMIEF MICH ARD M. PbVNN ENothEER

.O.E . , i wistown March 8, 1982 .a C6 a

10,m, ,V,.C g.. C .sL saDENT

, ,0,,,cx ..CcAnn JPN-82-28 "'***

THOMASR FREY es naL C wheek Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wa shington, D. C. 20055 Attention: Mr. Domenic Vassallo y O Operating Reactors Branch No. 2 gs Division of Licensing ( , god Subj ect : James A. FitzPatrick Nuclear Power Plant o ., m 1597 C3 Docket No. 50-333 ~

bfy gr%g s Containment Venting and Purging Cy h9ih M Ref ere nce s: 1. NRC letter T. A. Ippolito to G. T. Berry, /N a

0 dated December 15, 1981 / Q3 \ '

Dear Sir Reference 1 requested information concerning vent and purge line debris creens, and proposed Technical Specification changes regarding the Standby oas Treatment System (SGTS) and containment isolation valves.

The Power Authority's responses are contained in Enclosures 1, 2, and 3 to this letter. A description of the vent and purge line debris screens is provided in Enclosure 1. The se screens were installed during the Reload 4/ Cycle 5 refueling outage.

Emlosure 2 contains historical leakage test data for the FitzPatrick vent and purge valms. As provided for in Reference 1, the Power Authority is submitting these data in lieu of Technical Specification changes for ircreased surveillance. The Authority considers that these data adequately demonstrates valve integrity and that valve integrit r is assured without increased leakage testing.

As discussed in Enclosure 3, the Po"er Authority will propose Technical Specification changes to provide greater assurance of containment isolation in t he event of an accident. The Authority will also request a proposed 5

8203160176 820308

//

PDR P

ADDCK 05000333 PDR

Technical Specification change ho reduce the possibility of damage to the Standby Gas Treatment System during venting, as requested in Reference 1.

These proposed changes will be subnitted by April 15, 1982.

If you have any further questions, please do not hesitate to contact us.

Very truly yours,

\

Jbik9s ,

q1 J. . Bayne Se io Vice President Nuci Generation cc: Mr. J. Linville Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 Mr. Ron Barton United Engineers & Constructors, Inc.

30 S. 17th Street Philadelp hia, Pa. 19101

1 Enclosure 1 to JPN 28 VENT AND PURGE LINE GRATING COVERS l

During the Reload 4/ Cycle 5 refueling outage now in progress, the vent  :

and purge line grating covers were replaced. The existing grating was rewaved and new grating installed on the inside of penetrations X-25, 26A, 268, 71, 205 a nd 22 0. The gratings were constructed using 2" deep by 1/4" thick bearing bars 1-3/16" on center; 2" on center cross members with a minimum cross-cectional area of 0.07 square inches; and, 2" deep by 1/4" thick landing bars fully welded to all bearing bars and cross bars. A sketch of a typical grating is attacted.

The gratings were design a with openings of approximately 1-3/4" x 1-1/16". These openings were sized to prevent debris, large enough to inhibit valve closure, f rom reaching the valve. In addition, the drywell and torus are inspected for extraneous materials after work has been performed in t hese areas.

The grating were conservatively designed for both seismic and dynamic LOCA loads. The gratings will withstand a total load eqpal to the maximum pressure dif f erential between the containment and the atmosphere multiplied by the cross sectional area of the pipe. This is the load the grating would be subjected to in the unlikely event that it is completely blocked. The gratings were also designed to withstand the maximum dynamic LOCA load based upon the containment design response spectra.

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Enclosure 2 to JPN 2 8 VENT AND PUIGE VALVE LEAK TEST DATA Table 1 provides the leak rate test data for the FitzPatrick vent and purge valves as requested in Reference 1. Table 2 summarizes these data and provides the repair frequency for each valve. The interval between repairs was one year in only a single instance (27-AOV-ll4), and this repair was not required to meet acceptance criteria. All other repair intervals vary from 2 to as marry as 6 years. It should also be noted that these data identify repairs and adjustments to both valves and operators, and are not an indication of how frequently resilient seats were replaced.

The Power Authority considers these data adequate to demonstrate that Technical Specification changes, requiring quarterly leak rate testing and the replacement of resilient seats on a fixed interval, are not required to assure vent and purge valve integrity. e l

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Enclosure 2 - Table 1 l Valve Ieakage Data 27- ADV-lli & 27- A0V-112 PREOP: 74.58 SCFD (combined leakage for penetrations X-25/71) 1976: 75.50 SCFD (combined leakage for penetrations X-25/71) 1977: 340 SCFD 27-AOV-ll & 27-A0V-112 combined, 27-A0V-ll2 Rewor ked.

0.0 SCFD As Lef t, 27-A0V-111 & 27-A0V-ll2 combined 1978: 1.02 SCFD Accepted as Found 1980: 61 SCFD Accepted as Found 1981: Gross Ieakage As Found, 27-A0V-lli & 112 Reworked 27-AOV-113 & 27-A0V-ll4 NOTE: tested with 27-MOV-ll3 until final test of 1981 refueling outage.

PRE-OP: 28.68 SCFD combined leakage for penetrations X-26A/B 1976: 42.92 SCFD combined leakage f or penetrations X-26A/B 1977: Gross Leakage As Found, 27-A0V-ll3 Reworked 44.59 SCFD As Left 1978: 1.02 SCFD Accepted as Found 1980: 54.15 SCFD As Found, 27-AOV-ll4 Reworked (although not required) 1981: Gross Leakage As Found, 27-A0V-ll3 & 27-AOV-ll4 Reworked 0.276 SCFD As Left Page 1 of 4

Enclosure 2 - Table 1 Valve Leakage Data (continued) 27-ADV-115 & 27-AOV-116 PRE-CP: 36.29 SCFD Combined leakage for penetration X-220 1976: 34.90 SCFD Combined leakage for penetration X-220 1977: 80 SCFD 27- A0V-11; 27- AOV-ll6 Reworked (although not required) 4.96 SCFD As Left 1978: 1.02 SCFD Accepted As Found I

1980: 2.8 SCFD Accepted As Found

] 1981: 14.71 SCFD Accepted As Found 27- AOV-117 & 27-ADV-ll8 NOTE: tested with 27-MOV-117 until final test of 1981 refueling outage PRE-OP: 19 92 SCFD Accepted As Fbund 1976: 1.25 SCFD Accepted As Found l 1977: 1 14 SCFD Accepted As Found 1978: 6.28 SCFD Accepted As Found 1980: 18.07 SCFD Accepted As Fbund l

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! 1981: 19.9 SCFD Accepted As Found Page 2 of 4 i

l Enclosure 2 - Table 1 Valve Imakage Data (continued) i 27- AOV-131 & CAD-CV-68 (2A)

PRE-OP: 74.58 SCFD Combined leakage for penetrations X-25/71 1976: 75.50 SCFD Combined lea kage for penetrations X-25/71 1977: Gross leakage As Found, CV-68 ReworkeC.

33.69 SCFD As Left 1978: 185 SCFD As Found; CV-68 & 27-AOV-131A Reworked 200 SCFD As Left 1980: Gross Leakage As Found, CV-68 & AOV-131A Reworked 23 30 SCFD As Left 1981: 463 19 SCFD As Found, Reworked CV-68 3.62 SCFD As Left 27-AOV-131 & CAD-CV-69 (2B)

PRE-OP: 74.58 SCFD Combined leakage for penetrations X-25/71 1976: 75.50 SCFD Combined leakage for penetrations X-25/71 1977: 3.47 SCFD Accepted Iss Found 1978: 19.3 SCFD Accepted As Found 1980 19.80 SCFD Accepted As Found 1981: 22.9 SCFD Accepted As Found Page 3 of 4

Enclosure 2 - Table 1 Valve Leakage Data (continued) 27- A0V-132A & CAD-CV-67 (2C)

PRE-OP: 36.29 SCFD Combined leakage for penetration X-220 1976: 34.90 SCFD Combined leakage for penetration X-220 1977: 9.481 SCFD Accepted as found 1978: 150 SCFD As Ebunds CAD CV-67 Reworked 2.59 SCFD As Left 1980: 253 SCFD As Found, CAD-CV-67 Reworked 11 8 SCFD As Left 1981: 2.48 SCI *D Accepted as Found 27-A0V-132B & CAD-CV-70 (2D)

PRE-OP: 36.29 SCFD Combined leakage for penetration X-220 1976: 34.90 SCFD Combined leakage for penetration X-220 1977: 1.29 SCFD Accepted As Found 1978: Gross Leakage As Found; 27-AOV-132B t CAD-CV-70 Reworked 24.9 SCFD As Left 1980: 134 SCFD As Found; CAD-CV-70 Reworked 27.2 SCFD As Left 1981: 85.56 SCFD As Founds CAD-CV-70 Reworked 87.87 SCFD As Left Page 4 of 4 i I

Enclosure 2 - Table 2 VALVE REPAIR FREQUENCY Valve Tag tio. Valve Size (inches) Repairs Since Pre-Op Test 27- A0V-lll 24 1981 27-A0V-112 24 1977, 1981 27- A0V-ll3 24 1977, 1981 27-A0V-ll4 18 1980*, 1981 27- A0V-ll5 20 1977 27-A0V-ll6 20 1977*

27- ADV-ll7 20 ---- /;

27- A0V-ll8 20 ----

27- AOV-131A 1 1/2 1978, 1980 27-A0V-131B 1 1/2 ----

27- A0V-13 2 A 1 1/2 ----

27-AOV-132B 1 1/2 1978 27-MOV-ll3 2 ----

27-MOV-117 2 ----

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• Repair not required to meet acceptance criteria.

Page 1 of 1

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Enclosu e 3 to JPN-82 28 lI i 1- i PROIOSED TECHNICAL SPECIFICATION CHANGES 7

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' Enclosure 5 of Refererc,e 1jprovi$ed sample Technical Specifications regarding vent and purge / valves and containment isolation valves. The Power Aut'hority has reviewed thetie sansples and will propose changes to the FitzPatrick, Technical Specificethons' to provide greater assurance of cortainraent isolation in the - event of an ' accident. The proposed changes will not include additional leak rate testing or pariodic replacement of vent and purge val .re seats, as explained in Enclosure 2 to this letter.

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