ML19354D890

Proposed Tech Spec Table 3.7-1, Process Pipeline Penetrating Primary Containment & Table 4.7-2, Exception to Type C Tests to Replace Traversing in-core Probe Sys

ML19354D890
Person / Time
Site:	FitzPatrick
Issue date:	01/12/1990
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19354D887	List: ML19354D886 ML19354D889 ML19354D890
References
NUDOCS 9001230169
Download: ML19354D890 (6)

Text

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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION -

CHANGES REGARDING NEW TRAVERSING INCORE PROBE SYSTEM (JPTS-89-031) i i

i New York Power Authority -

JAMES A. FITZPATRICK NUCLEAR POWER PLANT 'l

. Docket No. 50-333 DPR-59 9001230169 900112 p DR ADock 05000333 ..

PDC  ;

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l JAFNPP ,.

TABLE 3.7-1 (Cont'd) -

PROCESS PIPELINE FENETRATING PRIMARY CONTAINMENT (Numbers o parentheses are keyeo to nurroers on tonowng pages; sgnal codes are wiw on sollowog pages)

Power to Location Ref. Power to isolation Normal Remarks a.d DryweR Open(5)(6) Group to Drywen Signal Oosing Time (7) Status Excephons Line isolated Penetration Valve Type (s) Oose(5)(6)

X-210A,B MO Gate Ac B Outside Ac RM Not app 5 cable Oosed Cors Spray Minimum Purre Flow X-16A,8 Ac A Outside Ac RM Not applicable Open Note (10)

Cors Spray to MO Gate Reactor X-15A,B MO Gate Ac A Outside Ac RM Not applicable Ocsed Note (10)

. Core Spray to Reactor A Inside Note (3) Rev Flow Not applicable Oosed Testable Check Wlve Core Spray to X-16A,8 AO Check (3)

Note (3,16)

Reactor X-210A,B MO Globe Ac B Outskje " Ac G,RM 45 See Oosed Core Spray Test to Suppasion Pool X-227A,8 Ac B Outside Ac RM- Not applicable Open Core Spray Pump MO Gate Sucten MO Plug Ac B ' nside' i Ac A.F.RM . . 30 See Open

' Drywc3 Equipment X-19 Drain Sump Discharge A.F.M Not applicable

~

DryweN Equipment X-19 AO Plug Air /Ac B Outsde Spring Oooed (17)

^

Drs.in Sump Discharge MO Plug Ac. 8 Inside ' Ac' A.F.RM 30 Sec . Open Drywe8 Floor X-18

DrLin Sump Discharge AO Plug B Outside . Spring A,F,RM Not appucable Open Drywe5 Floor X-18 '

Air /Ac ~

Crain Sump Discharge X-35A,B,C - Explosive Do A- Outsde De' RM Not applicable Open One valve on eachline TraveEng incore "

Probe Shear X-35A,B C Ac A Outside Ac ' A.F.RM Not applicable Open One valve on eachlino Trave 5ng incore SO ban Note (11)

Probe Ac A Inside .  : Ac _ 'L,RM 20 Sec . Open ~ ) Signal T" opens valve.

HPO - Turbine z X-11 MO Gate

) Signal *L* overrides and . -

1 Steam Supply

) closes valve.

HPO - Turbine X MO Gate De A. - Outside De L,RM 20 See Oosed ')

)

Steam Supply

- A.Te.di.eii Nob 1 1 201

JAFNPP o TABLE 4.7-2 EXCEPTION TO TYPE C TESTS ,

CONTAINMENT PENETRATION VALVE LOCAL LEAK RATE TEST PERFORMED PENETRATION FUNCTION NUMBER 35C Traversing 07NM-104C This valve is an explosive shear valve which cannot be Type C tested.

In Core Probe 37A Control Rod Drive SOV-120 Will not be tested as lines are sealed by process fluid.

378 (Inlet) SOV-123 37C AOV-126 37D CRD-108 38A Control Rod Drive SOV-121 WH not be tested as lines are sealed by process fluid.

38B (Outlet) SOV-122 38C AOV-127 38D 39A RHR Cont. Spray 10MOV41 A - This valve will be tested in the reverse direction.

39B RHR Cont. Spray 10MOV-318 This valve will be tested in the reverse direction.

45 Drywell Pressuro 16-1 AOV-101 A . This valve will be tested in the reverse direchon.

Sensing '

500 ' instrumentation - Various These instrument root valves are tested during a Type A test. '

Sensing DW Pressure

- Arnendment No.f.1 ,If,1[ 212

ATTACHMENT ll ,

SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION~

CHANGES REGARDING NEW TRAVER5iWG  :

INCORE PROBE SYSTEM (JPTS-84 ?31)-

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-q 1

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New York Power Authority

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 y

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Attachment 11 SAFETY EVALUATION  ;

Page 1 of 2

l. DESCRIPTION OF THE PROPOSED CHANGES C The proposed changes to the James A. FitzPatrick Technical Specifications revise Table 3.71, .

" Process Pipeline Penetrating Primary Containment," and Table 4.7 2, " Exception to Type C Tests." The changes are as follows:

l 1) Table 3.71, page 201 - delete penetrations X 35D and X 35E, r

2) Table 4.7 2, page 212 delete penetration X 35D. ,

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< ll. PURPOSE OF THE PROPOSED CHANGES The Traversing incore Probe (TIP) system is used to calibrate the Low Power Radiation Monitors (LPRMs). During the 1990 refueling outage the existing system will be replaced with a new state-4 of the art system. The new system willimprove overall TIP system reliability, availability, and ,

. accuracy.  !

The modification replaces the four existing TIP drive units with three drive units.. The helical shleid v cabling will be replaced with a titanium shield cable. Changing from a four channel system to a three channel system requires the use of one less containment penetration. As a result, penetration X 35D will be capped. The titanium shielding, which does not require a nitrogen ,

blanket, permits the removal of the TIP system's nitrogen purge equipment. Penetration X 35E, J which accommodated the TIP nitrogen purge line, will also be capped.  ;

lil. IMPACT OF THE PROPOSED CHANGES The proposed changes revise Tables 3.71 and 4.7 2 to delete two penetrations, X 35D and X 35E,- .

which will be capped as a result of the TIP system modification. The capping of these penetrations is not a safety concern because the replacement of an active isolation valve with a passive barrier is a more reliable containment isolation method. The capped TIP penetrations will-be subjected to a Type A integrated leak rate test with visual inspection prior to plant restart and periodic testing in accordance with the requirements of 10 CFR 50, Appendix J.

The changes do not alter the conclusions of the plant's accident analyses as documented in the FSAR or the NRC staff's SER nor are they considered a significant hazard consideration.-

IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION l

Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with this proposed amendment would not involve a significant hazards consideration, as defined in 10 CFR 50.92, since the proposed changes would not: l

1. Involve a significant increase in the probability or consequences of an accident' previously evaluated. The changes update Tables 3.71 and 4.7 2 In support of a- ,

plant modification which caps penetrations X 35D and X-35E. These penetrations L will be leak tested during the integrated leak rate test of the containment in ~ -(

l- accordance with the requirements of 10 CFR 50, Appendix J. The capping of these

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Attachment 11 SAFETY EVALUATION Page 2 of 2 i

penetrations do not impact the plant's accident analyses as documented in the j ,

. FSAR or the NRC staff's SER.

2. create the possibility of a new or different kind of accident _ from those previously evaluated. . The capping of these two containment penetrations improves containment isolation because a passive barrier is less likely to fall than an active isolation valve.' These changes do not introduce any new active failure modes and

, can not create a new or different kind of accident..

3. Involve a significant reduction in the margin of safety. The proposed changes cap .

two penetrations which are no longer required by the TIP system. These changes do not reduce the margin of safety, since a passive barrier is a more reliable method of containment isolation then an active isolation valve. .. j l

V. IMPLEMENTATION OF THE PROPOSED CHANGES ,

a implementation of the proposed changes will not impact the ALARA Program at FitzPatrick, nor will the changes impact the environment.

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VI. CONCLUSION These changes, as proposed, do not constitute an unreviewed safety question as defined in 10 j CFR 50.59. That is, they: I

a. will not increase the probability of occurrence or the consequences of an accident or

[ . malfunction of equipment important to safety previously evaluated in the safety analysis i j report;

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b. will not increase the possibility for an accident or malfunction of a different type from any q evaluated previously in the safety analysis report l

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c. willilot reduce the margin of safety as defined in the ba'sis for any technical specification; and -)

l j d. Involves no significant hazards consideration, as defined in 10 CFR 50.92.  !

l Vll. REFERENCES 1 l

1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Sections 5.2.4.6 and 7.5.9.

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2. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972 and Supplements. .

3. James A. FitzPatrick Nuclear Power Plant Traversing incore Probe (TIP) System  :;

Upgrade Conceptual Design Package Modification Number F188-253, December

. 1989.

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