ML19341A804

Forwards Info Clarifying Util 800102 Response to NUREG-0578 Item 2.1.4,in Response to Concerns of Resident Inspector Re Primary Containment Isolation Sys.Nonessential Sys Automatically Isolated Upon Containment Isolation Signal

ML19341A804
Person / Time
Site:	FitzPatrick
Issue date:	01/23/1981
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Ippolito T Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 JPN-81-9, NUDOCS 8101280117
Download: ML19341A804 (19)

Text

{{#Wiki_filter:4 POWER AUTHORITY OF THE STATE OF NEW YORK to CoLuusus CIRCLE NEW YORK. N. Y. loo 19 (2128 397 6200 agonat r. stmay oesnatYNo orr"ican fmusttEs JOHN W. BOSTON JOHN s.DysON nasics a nacree or ao**a ana"'o== aconos c.iNoacts JQ.(PH R. SCHMIEDER wict cosalansaN anscutivs vica PRE 91oENT & cMtEP RICH ARD M. FLYNN ao. car i. Miutour' January 23, 1981 'taov w *mc'Aia samion vict possioENT Famosaicic. etanic JPN-81-9 g,c;;;r,,riaaacia6 THOM AS R. FREY Director of Nuclear Reactor Regulation - l'2$.".'i "'.*.'a6 U.S. Nuclear Regulatory Commission Washington, D. C. 2055S Attention: Mr. Thomas A. 7ppolito, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0578, Item 2.1.4 Clarification

References:

1. PASNY letter from P. J. Early to T. A.

Ippolito (JPN-80-1) dated January 2, 1980

2. NRC letter from H. R.

Denton to All Operating Nuclear Power Plants dated October 30, 1979

3. NRC letter from T. A.

Ippolito to G. T. Berry dated March 25, 1990

Dear Sir:

The purpose bf this letter is to clarify the Authority's response to NUREG-0578 Item 2.1.4 as contained in Reference 1. It is our understanding that the response provided therein does not accurately reflect the Authority's position as noted in the attached report. The Authority considers that the J. A. Fitz-Patrick Plant is in compliance with NUREG-0578 Item 2.1.4 as clarified in Reference 2 and discussed in the aforementioned report. The attached report identifies an item of non-co nformance which, as noted in Reference 1 Item 2.1.4, was corrected by appropriate modifications. It further concludes that non-essential systems, except those that are considered closed within the reactor containment (i.e., systems that do not com-municate with either the reactor coolant system or the containment atmosphere), are automatically isolated upon a containment isola-tion signal. As noted in Reference 3, this design was found acceptable based on the review of this report conducted by members of your staff during a site visit on March 13, 1980. 9 ( \\ 8101280 W ep

G This clarification is being forwarded as a result of certain concerns expressed by the J. A. FitzPatrick NRC Resident Inspector during a routine inspection. Because of the need for this additional clarification, the Authority is currently reviewing the attached report in detail with the Architect Engineer. Additional information will be forwarded to you as appropriate. Should you have any' questions, please do not hesitate to contact us. Very truly yours, J. P.~Bayne' Senior Vice P' resident - Nuclear Generation Encl. d t er

Item 2.1.4 - NUREG 0 57 8 NRC Position 1. All containment isolation system designs shall comply with the recommendations of SRP 6.2.4; i.e., that there be diversity in the parameters sensed for the initiation of containment isolation. 2. All plants shall give careful reconsideration to the definition of essential and non-essential systems, shall identify each system determined to be essential, shall identify each system determined to be non-essential, shall describe the basis for se'lection of each essential system, shall modify their contain-ment isolation designs accordingly, and shall report the results of the re-evaluation to NRC. 3. All non-essential systems shall be automatically isolated by the containment isolation signal. 4. The design of control systems for automatic containment isolation valves shall be such that resetting the isolation signal will not result in the automatic reopening of containment isolation valves. Reopening of containment isolation valves shall require deliberate operator action.

Response

1 The JAF Primary Containment Isolation system complies with Position 1 of NUREG 0578 by providing two or more diverse para-meters to initiate automatic isolation of all non-essential isolation valves. Isolation systems, valves,.and their respective isolating signals are listed in Appendix 1. Only automatic isciation *ulves of non-essential system have been reviewed. Valves that m;y close by process action (reverse flow) or by remote manual creration have not been included in this report. This statement is based on a review of elementary diagrams of all isolation valves listed on Table 7.3-1 of the JAF FSAR and those listed on the LEAK RATE TEST table. A comparison was made be-tween the isolation signals shown on the elementary diagrams and those shown on Table 7.3-1. There was general agreement be-tween the diagrams and the table except in the case of valves 2-39 and 2-40 where the GE diagrams had isolation signals B and i C initiating automatic closing of the valves while Table 7.3-1 had the same two signals 3 and C, but also had additional sig-nals D, E and P. 1 I i l i a

i Page 2 i 2. The design basis for the containment isolation systems is discussed in FSAR Sections.5.2 and 7.3. The following defini-tions are provided for the purposes of determining which sys-tems are non-essential and should therefore be automatically isolated: Essential systems are defined as those Engineered Safety Features (ESF) systems with fluid lines penetrating the primary containment, which must remain operable following a design basis event (DBE). Non-essential systems are those non-ESF fluid lines pene-trating the primary containment which are not required to be operable following a DBE. A list of all ESF systems is presented in the FSAR in response to AEC Question 7.6 of 1/12/72. Table 2.1.4-1 is the subset of those systems with fluid penetrations into the primary con-tainment, defined as essential systems. As noted on Table 2.1.4-1, those essential systems not required in the snort-term following a DBE are automatically isolated, and remote-manually or automatically initiated when needed. A complete list of containment peretrations is provided in FSAR Table 7.3-1, and in JAFNF? Technical Specifications Table 3.7-1. The same list with additional 20tc (showing shutdown, post acci-dent and power failure valve position) was submitted by letter (JPN-79-7 6, November 21, 1979) to W. C. Kane of the NRC Bulletins and Orders Task Force. Table 2.1.4-2 is a list of non-essential systems, comprised of those fluid systems penetrating the con-tainment not listed in Table 2.1.4-1 as essential systems. All non-essential systems, except those noted in Table 2.1.4-2 as close_d systems (and therefore not a high probability pathway for radioactivity release' to the environment), are automatically isolated following a DBE. No containment isolation design modifications are required for either the essential or non-essential systems defined above. e

P ~ v Page 3 TABLE 2.1.4-1 ESSENTIAL SYSTEMS - ESF SYSTEMS WITH FLUID LINES PENETRATING PRIMARY CCNTAINMENT ESSENTIAL SYSTEM FSAR DESCRIPTION SECTION(S) Residual Heat demoval 6.4.4, 7.4.3.5 (LPCI Mode) Reactor Core Isolation Cooling 4.7.5 Core Spray 6.4.3, 7.4.3.4 Primary Containment Atmospheric 5.2.3.8 Control (Note 1) High Pressure Coolant Injection 6. 4.1, 7.4.3.2 Emergency Service Water (Note 2) 9.7.1.3 s Standby Liquid Control (Note 3)

3.9.3 N0mnd

1. This system is automatically isolated af ter a DBE and remote-manually opened for CAD nitrogen dilution approximately 24 hours after a DBE. CAD purge is remote-manually opened a approximately 52 days after a DBE. 2. The ESW system is automatically isolated after a DBE and auto-matically actuated on loss of pressure in the RBCCW system. 3. The SLC system uses check valves for isolation which close on reverse flow. i

i l Page 4 TABLE 2.1.4-2 l NON-ESSENTIAL SYSTEMS - NON-ESF SYSTEMS WITH FLUID LINES PENETRATING PRIMARY CONTAINMENT NON-ESSENTIAL SYSTEM FSAR DESCRIPTION SECTION(S) Main Steam 4.5.3, 4.6.3, 4.11.4 Feedwater 4.11.4, 10.8.3 Residual Heat Removal 4.8.6.4 (Shutdown Cooling Mode) Residual Heat Removal 4.8.6.2 (Containment Spray Mode) Reactor Water Cleanup 4.9.3 Radwaste (Floor and Equipment 9.13.3 Sump Pumps) Service Air 9.11.3 Instrument Air (Note 1) 9.11.3 3reathing Air 9.11.3 Reactor Building Closed Cooling 9.5.3 Water (Note 1) Drywell and Torus Pressure Sensing 5.2.4.4 Reactor Recirculation Loop Sample 9.14.3 Recirculation Pump Mini-Purge 4.3.4 (Note 2) CRD Hydraulic System (Note 2) 3.5.5 Traversing Incore Probes (Note 1) 7.5.9.2 NOTES: 1. These systems do not automatically isolate, but are closed systems inside containment. 2. These systers do not automatically isolate, but are closed -systems outside containment, and isolate on reverse flow.

Page 5 4 3. All non-essential systems and valves at JAF are automatically isolated by diverse containment isolation signals. Isolation signals, valves and system are listed in Appendix 1. The only. exceptions to the above statement are systems which utilize reverse flow check valves to prevent flow out of con-tainment. 4. Elementary diagrams of all non-essential isolation valves have been reviewed for compliance with requirement that the valve not automatically open when resetting an isolation signal. All non-essential automatic isolation valves at JAF have been furnished with opening circuits which will not open automatically when the isolation signals have been cleared and the reset switch operated. The operator must take deliberate action to open valves by setting spring return switches to the "0 PEN" position e.nd maintained contact switches first to the "CLOSE" position and then to the "OPEN" position. The exceptions to the above are noted below: Exception: Reactor Water Sample Valves 02-AOV-39 and 40 will open after isolation signal is manually reset if their respec-tive control switches are left in the AUT0/0 PEN position. This condition will be remedied by connecting a normally closed contact from the control switch into the reset circuit of the isolation signal relay. This requires the operator to place the control switch in the "CLOSE" posi-tion before he can reset the isolating signal. To open the valve, the operator must then place the cottrol switch in the "OPEN" position. r 1 i

i i l Appendix 1 ISOLATION SIGH S AND SYSTEMS 1.0 The following isolation valves and systems will automatically isolate on receipt of isolation signals 3, C, RM. (See Ap-pendix 2 for explanation of the isolation signals) .1 Reactor Water Sample Valves 2.0 The following isolation valves and systems will automatically isolate on receipt of isolation signals A, F, RM. (See AP-pendix 2 for explanation of the isolation signals) .1 RHR reactor shutdown cooling supply * .2 RHR reactor head spray * .3 Drywell equipment drain discharge .4 Drywell floor drain discharge .5 RHR to Radwaste .6 Traveling Incore Probe 3.0 The following isolation valves will automatically isolate on receipt of isolation signals A, J, RM. (See Appendix 2 for explanation of the isolation signals) .1 Reactor Water Cleanup Valves 12-15 .2 Reactor Water Cleanup Valves 12-18 (plus signals V & Y) .3 Reactor Water Cleanup valves 12-80 * (plus signals V & Y)

• Closed during normal plant operation.

Appendix 1 1 Page 2 4.0 The following isolation valves and systems will automatically isolate on receipt of isolation signals B, C, D, E, P. (See Appendix 2 for explanation of the isolation signals) .1 Main Steam Line Drain Isolation Valves .2 Main Steam Line Inboard Isolation Valves .3 Main Steam Line outboard Isolation valves 4 5.0 The following isolation valves and systems will automatically isolate on receipt of isolation signals A, F, Z. (See Ap-pendix 2 for explanation of the isolation signals) .1 Pressure supp2 ;sien chamber exhaust valve bypass * .2 Pressure suppression cha=ber purge inlet .3 Pressure suppression chamber main exhaust .4 Drywell exhaust valve bypass * .5 Primary containment atmosphere sampling supply .6 Pressure suppression chamber atmosphere sampling supply .7 Primary containment / pressure suppression chamber atmosphere sampling return .8 Drywell Purge Inlet .9 Drywell Main Exhaust .10 CAD /MKUP Drywell Isolation .11 CAD /MKUP Torus Isolation .12 Air Part. Det. & Gas Sampling

Appendix 2 Page 2 6 Signal Description T Low reactor pressure permissive to open core spray and RHR-LPCI valves U High reactor vessel pressure - close RHR - shutdown cooling valves and head cooling valves V High temperature at outlet of Reactor Water Cleanup System nonregenerative heat exchanger Y Standby Liquid CF..urol System actuated Z* Reactor buil'> ; ventilation exhaust high radiation RM

• Remote manual switch from control room (automatic Group A and Group 3 isolation valves are capable of remote manual operation from the control room except containment purge valves and sample valves).

1 I l l

• These are the isolation functions of the Primary Containment and Reactor Vessel Isolation Control System; other functions are given for information only.

Appendix 2 ISOLATION SIGNAL CODES Sicnal Description A* Reactor vessel low water level - (A scram occurs at this level also. This is the higher of the two isola-tion low water level signals) B* Reactor vessel low water level - (This is the lower of the two 1cw water level signals. Main steam line isolation occurs at'this level.) C* High radiation - main steam line D

• Line break - main steam line (steam line high steam flow)

E* Line break - main steam line (steam line high temperature) F* High drywell pressure G Reactor vessel low water level or high dryvell pressure (Emergency Core Cooling Systems are starte.d) H Line break in recirculation loop - close corresponding RHR-LPCI loop valves J* Line break in Reactor Water Cleanup System - high space temperature K* Line break in RCIC System steam line to turbine (high steam line space temperature, high steam flow, low steam line pressure, or high turbine exhaust pressure) L* Line break in HPCI System steam line to turbine (high steam line space temperature, high steam flow, low steam line pressure, or high turbine exhaust pressure) M Line break in RER shutdown and reactor vessel head cooling (high space temperature used for alarm only, no auto closure) P* Low main steam line pressure at inlee to main turbine (RUN mode obly) S Low drywell pressure

• These are the isolation functions of the Primary Containment and Reactor Vessel Isolation Control System; other functions are given for information only.

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