Text

Forwards Updated Status of Util Program Re Reg Guide 1.97, Rev 3, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Access Plant & Environ Conditions During & Following Accident
	ML20246M636
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	09/01/1989
From:	Tremblay L; VERMONT YANKEE NUCLEAR POWER CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 BVY-89-80, NUDOCS 8909070213
	Download: ML20246M636 (32)
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jVERMONTLYANKEE

" 89-8 I

NNUCLEAR POWER CORPORATION s

y Ferry Road, Brattleboro, VT 05301-7002 m,, m y

ENGINEERING OFFICE I

' 580 MAIN STREET y..

September 1, 1989 gotrou,ugoi7,o

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- United-States Nuclear, Regulatory Commission Document Control besk l>

. Washington,.DC 20555

. Ref er ences : -

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter, VYNPC to USNBC, FVY 87-77, dated August 11,~1987, "NUREG-0737, Supplement No. 1 - Regulatory Guide 1.97, Program Status" (c) -Letter, VYNPC to USNRC, FVY 88-064, dated July 28, 1988, "NUREG 0737, Supplement No.

l'- Regulatory Guide 1.97, Program Status Clarification"

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Subject:

NUREG-0737, Supplement No. 1 - Regulatory Guide 1.97 Program Status

Dear Sir:

-The' purpose of this letter'is to provide an updated status of the Vermont Yankee Program pertaining to Regulatory Guide 1.97, Revision 3,

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Land Environment Conditions During and Following an Accident."-

In prior correspondence, Vermont Yankee detailed our continuirg efforts to address the requirements of Regulatory Guide 1.97.

In our August-11, 1987 submittal [ Reference (b)], we provided the results of our plant-specific engineering assessment of Regulatory Guide 1.97, Revision 3, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environment Conditions During and Following an Accident." By letter, dated July 28, 19s8

[ Reference (c)}, Vermont Yankee provided a program status clarification of the l

Regulatory Guide 1.97 equipment upgrades with respect to various nonessential recorders.

Consistent with prior submittals, this letter provides an updated status of equipment.in two attachments.

-Attachment A - Qualification Summary (subdivided into four sections).

1.

Equipment which is in full agre'ement with Regulatory Guide 1.97 requirements.

2.

Equipment where range, environmental qualification, or other attributes have been determined on a plant-specific basis, to be appropriate for Vermont Yankee. Where these attributes differ from those shown in the regulatory guide, justification of the appropriateness of the attributes selected is provided.

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'3h Equipmtnt'which shall'be modified or upgraded. in order to provide adequate range,. environmental-qualification,'o'r other:

characteristics.~. Presently, no instrumentation is" listed here.

-4.

Equipment-which has bean deleted from Vermont Yankee (s 1987'an 1988 Regulatory Guioi 1.97 List of Instrumentation.- This equipment has Lbeen removed asi result of further ' developments 'in operating-procedures and.the Verment Yankea Equipment' Qualification Program.

u B - Regulatory Guide 1.97. Instrumentation Matrix.

Both; Attachments A and B have been expanded. ~This expansion' includes additional information pertaining to the instrumentation associated with the:

s regulatory guide.. Additional discussion has been provided where exceptions to the regulatory guide have been taken,(Attachment A. Table 2).

Where deemed necessary, Vermont Yankee's position regarding regulatory guide requirements J

has also been more clearly discussed. Many of.the revisions made to the 6;

attachments are'intendedito improve.its completeness and clarity.

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.Thislupgraded submittal incorporates modifications performed.during the z;

. cycle 13. 19891 refueling outage. These modifications included the deletion of tvarious recorders [ Reference (c)], upgrades to the Torus and. Drywell pressure.

-indicators-to.' resolve Human Engineering Deficiency.(HED) findings and x

' upgrades to the LocallPower Range Moultor-(LPRM) power supplies. Changes to

' Appendix A, since'the August 11,1987. subn.ittal, are denoted by a bar in: the

right margin. However,.due to the nature of the revisions, changes to.

Attachment B, since the Auguat-11,31987' submittal, are not identified.

Attachment-B is considered tp be completely revised.

We_ trust that the enclosed status update information is satisfactory and assists'your review of the-Vermont Yankee Regulatory Guide 1.97 Program.

-Should you have any questions or require additional information concerning this. matter, please contact this office.

Very truly yours, VE ONT YANKEE NUCLEAR 20WER CORPORATION l.

Leonard A. Tremblay, Jr. g Licensing Engineer LAT/bil/0435w

. Enclosures

!cc: USNRC Region I Administrator c

'USNRC Resident Inspector - VYNPS JUSNRC Project' Manager - VYNPS 4

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Page 1 of 18 ATTACHMENT A Qualification Summary The following is a list of Post-Accident Monitoring (Regu*.atory Guide 1.97)

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instrumentation.

It is divided into four sections as follows:

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Section_1 lists the instrumentation which is in full compliance with the 1

requirements as specified by Regulatory Guide 1.97.

o Section_J details equipment which has been evaluated on a plant-specific l

basis to provide the information required to support safe shutdown. This equipnent may differ in range, environmental qualification, or other j

attributes from the guidance in Regulatory Guide 1.97.

However, the analysis performed ensures that this equipment supports the requ' red safety functions specified in the Vermont Yankee Environmental Qualification Program and.onforms to the new Symptom-Based Emergency Operating Procedures.

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o Section_3 details additional instrumentation needed. This additional l

instrumentation could consist of intirely new instrument channels or 1

existing instrument. channels which require some upgrading. A11' equipment being installed will be qualified in accordance with the appropriate Vermont Yankee specific Design and Qualification Criteria category. At present, there is no equipment associated with Section 3.

o Ee.c11cn_4 details the instrumentation which has been deleted from the l

Regulatory Guide 1.97, List of Instranentation. Vermont Yankee origine.11y considered this equipment within the scope of Regulatory Guide 1.97.

However, follcuing further development of operating procedures and the Vermont Yankee Equipment Qualification Program, some l

equipment was no longer required to be operational. Consequently, it has been removed from the Regula. tory Guide 1.97 Instrumentation Matrix (Attachment B).

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Environmental Qualification requirements are determined in the Vermont Yankee EQ Program.

In determining envizcumental qualification requirements, all design basis events, ns docufuented in Chapter 14 of the Vermont Yankee final l

Safety Analysis Report (FSAR), have been addressed. Also addressed are High j

Energy ideae Breaks (HELEs) outside containment and ficoding. This 19

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consistent with the intent of 100FR50.49.

The method f or identifying electrical equipment within the scope of j

Paragraphs (b)(1) and (b)(2) of 10CFR50.49 (i.e., safety-related., as well as nonsafety-related electrical equipment relied upon to remain functional or whose f ailure under postulated environmental conditions could prevent satisf actory accomplishment of safety functions during and follewf:ng design-bacia accidents) is described and dccu:nented in the Vermont Yankee EQ Pro 6; ram.

This included:

l (a) Identification of general design criteria consistent with Vermont

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f Yankee's plant-specific design and 10CIG50.49; j

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Page 2 of 18 1

I (b) Defining required safe shutdown safety functions for design-basis accidents utilicing shutdown sequence diagrams based upon existing emergency operating procedures and the Vermont Yankee FSAR; (c) Identification of the major electrical components required for each postulated accident in potentially harsh environments which are relied upon to operate (or to not fail) for required safety functions. These components were identified by reviewing Plant Piping and Instrumentation Diagrams (P&lDs); and (d)

Identification of the remaining electrical components in potentially harsh environments (associated with the major required electrical components) that are relied upon to function, or whose f ailure could impact any required safety functions or mislead the operator such that required safety functions could be jeopardized, These components were identified by reviewing plant electrical Control Wiring Diagrams (CWDs).

In addition, a field walkdown inspection of all major components and associated equipment was performed to ensure accuracy and completeness.

I The method used for identifying electrical equipment within the scope of Paragraph (b)(3) of 10CFR50.49 (i.e., "certain post-accident monitoring equip?cnt") included the review of Symptom-Based Emergency Operating Procedures to identify a conplete list of associated display instrumentation.

The instrumentation necessary to determine that a system is performing; its safety function is included in the list of post-accident monitoring instrumentation.

A review for plant-specific Type A variables was conducted utilizing the Symptom-Based Emergency Procedures. These procedures are living documents; as future revisions to the E0Ps modify display instrumentation requirements, changes to the instrument list will be made accordingly.

The Category 1 variables, which require redundancy, have been evaluated to ensure that a single failure will not result in information ambiguities that could lead operators to defeat or fail to accomplish a required safety J

i function. One or more of the following means is available to access plant status of the affected parameter:

(a) Crosschecking with an independent channel that monitors a different variable bearing a known relationship to the failed monitoring channel.

1 (b) Perturbing the measured variable to determine the failed channel by i

observing the response on each instrument.

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(c) Operating procedures.

Real time display for Category 1 parameters is provided by Control Room indication (indicators and/or recorders) and computer display. A review of j

plant-specific requirements indicates that the only parameters which require h

trend recording are reactor pressure and reactor water level. However, a l'

variety of ndditional recording and plant conputer inputs are available.

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Page 3 of 18 It should be noted that Category 1 variable separation at Vermont Yankee is in accordance with the Ecrmoni_Janhet J rnund l ulca_.far._ Separation _and Identification _oL_Reaciar Protect 1Dn_ Dud _Ilaf.Ruard..Synigma. This is the criteria utilized during the original design und construction of the plant.

Its use in this application is, therefore, accepta.ble.

Attachment B is the Regulatory Guide 1.97 Equipment Matrix.

It is arranged in e manner which allows identification of requirements and abilities. Where e requirement is not applicable, it is so noted with an N/A uader the appropriate column. An explanation of an N/A status is provided in Attachnent A, Section 2.

Where the regulatory guide does not require specific documentation, N/R is inserted rader the appropriate column. 'Ihe basis for N/R status is provided by Table 1 of the Regulatory Guide. Vermont Yemkee interprets the documentation and redundancy requirements as follows:

EQ Sairmic QA B.edstdancy Category 1 Required Required Required Required Category 2 Required N/R Required N/R Category 3 N/R N/A N/R N/R f

Under the appropriate columns, a Yes or No is indicated to reflect if the documentation or redundancy requirements are adequately addressed.

If a No is listed, justification for its acceptability is prcvided in Attachment A, Secticen 2.

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Ins 1rumen'tation in Full Compliance With Regulatory Guide 1.97 4

The following instrumentation currently installed at V.ermont Yankee fully complies with Regulatory Guide 1.97 requirements:

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. Reactor Pressure 1

A2 Reactor Vessel Level 1

A4 Drywell Pressure 1

t A5 Drywell Temperature 1

A6 Torus Pressure 1

A7 Torus Water Temperature 1

A8 Torus Water Level 1

A9 Torus Airspace Temperature 1

B2 Control Rod Position 2

B3 RCS Soluble Boron Concentration 2

B6 RCS Pressure 2

B10 Primary Containment Isolation Valve Position 2, 3 Indication C2 Primary Coolant Analysis (gamma spectrum) 2 C4 RCS Pressure 2

l C5 Psdmary Containment Area Radiation 2

07 Suppression Pool Wide-Range Level 2

C9 RCS Pressure 2

010 Dryvell Pressure 2

C11 Containment /Drywell Hydrogen Concentration-2 C12 Containment /Drywell Oxygen Concentration 2

D1 Main Feedwater Flow 2

l D3 Suppression Chaniber Spray Flow 2

D6 Suppression Pool Water Temperature 2

1 D8 Drywell Spray Flow 2

DIO Primary Safety Relief Valve Position - ADS 2

D16 LPCI Flow 2

D19 RHR System Flow 2

D23 Radwaste System 2

D25 Standby Power Status 2

El Primary Containment Area Radiation 2

E3 Radiation Exposure Rate (Safety Access Areas) 2 E10 Particulate / Halogens 2

Eli Airborne Radichalogens 2

P E1.3 Isotopic Analysis 2

E14 Wind Direction 2

EIS Wind Speed 2

E17 Primary Coolant Sample (Except pH) 2 E18 Containment Air Sample 2

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Fully satisfies the requirements for Type "A" variables by Regulatory L

Guide 1.97.

The Vermont Yankee Emergency Operating Procedures determined I

ithe need for the variable and the acceptance criteria.

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~Page 5 of 18 E ff Notes (Continued).

27. Fully satisfies the' requirements as defined by Regulatory Guide 1.97.

'This includes enveloping the stipulated range and category requirements.

3.

Post-LOCA primary containment isolation valve position is required for a ten-minute. duration. As determined by the Vermont Yankee Environmental Qualification Manual, the following isolation valve position indication is required:

Valve Tag No.

Service FS0-109-76A, B DW Radiation Monitor to Torus Isolation VG-26 DW Radiation Monitor Isolation MOV-23-15, 16 HPCI Steam Supply Isolation TIP BV TIP Ball Valves TIP SV TIP Shear Valves ADV-2-80A, B, C, D Main Steam Isolation (Inboard)

A0V-2-86A, B, C, D Main Steam Isolation (Outboard)

FCV-2-39,-40 Reactor Sample Line Isolation MOV-2-74, 77 Main Steam Drain Isolation SB-16-19-06 DW Vent to SBGT Isolation

.SB-16-19-06A 07A DW Vent Isolation SB-16-19-06B, 07B Torus Vent Isolation

.SB-16-19-07 DW Vent to Stack Isolation SB-16-19-08 Purge Supply to DW Isolation SB-16-19-09 Air Purge Supply From RB Isolation SB-16-19-10 Purge Supply to Torus Isolation SB-16-19-11A, B DW-Vacuum Relief Isolation SB-16-19-23 N2 Purge Supply Isolation V16-20-20; 22A, B N2 Makeup Isolation A0V-20-82, 83 DW Floor Drain Isolation A0V-20-94, 95 DW Equipment Drain Isolation MOV-13-15, 16 RCIC Turbine Steam Supply Isolation MOV-12-15, 18 RWCU Supply Isolation MOV-12-68 RWCU Return Isolation MOV-10-33 RHR Head Spray Isalation MOV-10-57, 66 RHR to Radwaste Isolation A0V-72-38A, B DW Air Compressor Suction Isolation

'SB-9, 10, 11, 12 RB HVAC Isolation NG-11A, B CAD Purge Supply Isolation.

NG-12A, B CAD Purge Supply Isolation NG-13A, B CAD Purge Supply Isolation VG-9A, B CAD Vent Isolation VG-22A, B CAD Vent Isolation VG-23 Drywell Radiation Monitor Supply Isolation VG-24 Torus H /02 Sample Isolation 2

VG-25 Torus H /02 Sample Isolation 2

VG-33 Torus H /02 Sample Isolation 2

VG-34 Torus H /02 Sample Isolation 2

VG-75A1, A2 Torus H /02 Sample Isolation 2

VG-75A3, A4 Torus H /02 Sample Isolation 2

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Page 6 of 18 Valve 4.

IagJNai service VG-75B1, B2 Drywell H /02 Sample Isolation 2

VG-75C1, C2 Drywell H /02 Sample Isolation 2

VG-75D1, D2 Drywell H /02 Sample Isolation 2

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isolate the primary containment.. These valves also provide primary containment isolation valve position indication. They are as follows:

Valve lag No.

Service

.MOV-10-13A, B, C, D RHR Pump Suction From Torus Isolation MOV-10-16A, B RHR Minimum Recirculation to Torus Isolation MOV-10-25A, B

.RHR LPCI to Reactor Isolation MOV-10-27A, B RHR LPCI to Reactor Isolation MOV-10-26A B RHR to DW Spray Isolation MOV-10-31A, B RHR to DW Spray Isolation MOV-10-34A, B RHR to Torus Isolation MOV-10-38A, B RHR to Torus Spray Isolation MOV-10-39A, B RER to Torus Spray Isolation MOV-14-05A, B CS Minimum Recirculation to Torus Isolation MOV-14-07A B CS Suction Isolation MOV-14-11A, B CS to Reactor Isolation MOV-14-12A, B CS to Reactor Isolation MOV-10-17 Shutdown Cooling Reactor Isolation VG-26 Containment Radiation Monitor Isolation 7791R

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Page 7 of 18-l' 2.

Equipment _Reiermined to be Approp11 ale.on a Plant-Specific Basia This section details equipment currently existing at Vermont Yankee.'how it deviates from the regulatory guidance, and a justification for the existing equipment acceptability. This equipment is:

ltem Service Results B1 Neutron Flux Per the Vermont Yankee EQ Program, only the Local Power Ratge Monitors (LPRMe) l are required to verify scram, not SRM/IRM equipment. This is based on a position that indication of neutron flun down to one percent power (rather than 10-0 percent power) is sufficient to l

determine that a successful scram has occurred. For accidents, a successful reactor scram by the control rods is anticipated even given a worst-case single failure. A failure to scram event (ATWS) is nat considered to be an accident in which harsh environments develop.

It is Vermont Yankee'r, position that the LPRMs are adequate to verify a scram and reactor shutdown.

B4 Coolant Level Regulatory Guide 1.97 requires a range from the bottom of the core support plate to the lesser of the top of the vessel or the centerline of the main steam line. The top of active fuel is used as the 0" reference for level indication. Based on that, the bottom of the core support plate is at approximately -154 inches; centerline of the main steam line is approximately

+244 inches; approximately 500 inches to the vessel top. The monitored range is 1200 inches. The lower range requirement is enveloped. The increasing range is approximately 44 inches less than the requirement.

However, it is the widest' range which can reasonably be monitored. This is due to the locations of the existing instrument tap locations. Should level exceed +200 inches and fill the vessel, the operator will have indication of increasing reactor pressure. The High Pressure Injection Systems would have automatically shut down due to high l

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L water level long before reaching the main steam line.

Based on the above discussion, and a review of the E0Ps, it is Vermont Yankee's position that the 1200" range is acceptable.

l BS Core Temperature In-core thermocouple do not presently 03 exist at Vermont Yankee. The intent of these instruments is to verify adequate water level / core cooling. Water level issues were addressed via Generic Letter 84-23. At that time, it was determined that in-core thermocouple were not required to ensure adequate water level / core cooling. Furthermore, this parameter was determined to be not required at this time (SECY 82-11).

Therefore, it is Vermont Yankee's position that this parameter will not be included at this time in the Regulatory Guide 1.97 submittal B7 Drywell Narrow-Regulatory Guide 1.97 requires both B9 Range Pressure drywell narrow-and wide-range pressure C8 measurement. Drywell narrow-range D4 pressure transmitter, PT16-19-28, is a single channel instrument. The wide range pressure transmitters, PT16-19-29A/B, encompass both the narrow-and wide-range requirements.

These transmitter loops meet the requirements for Category 1 variables.

It is Vermont Yankee's position that narrow-range drywell' pressure is not needed post-LOCA due to the fact that once the LOCA has been controlled, the

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drywell will not repressurize. However, if that were to happen, any changes in pressure will be disployed in the Control Room via the wide-range instruments. Therefore, it is not j

necessary to provide Category 1 instrumentation for narrow-range pressure.

It is Vermont Yankee's position that PT16-19-29A/B instrument loops satisfy the intent of these four l

post-LOCA variables.

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Drywell Sump Level

-The drywell-semp leve'l uses level

- C6 switches to start /stop' pumps during normal operation. Regulatory Guide 1.97-requires continuous. sump level indication from'the bottom to the top.

The existing' configuration is designed to detect and measure leaks in the drywell by measuring both the sump pump running time and the' time between pump.

initiation with external pump monitoring

. equipment. During a LOCA, drywell. sump level is ineffective because the sump will fill and. overflow into the torus.

The torus is monitored by an c

environmentally qualified level measurement system. Additionally, drywell pressure is also monitored by environmentally qualified instrumentation which will indicate a

.line break in the drywell before the torus level indicates a rise.

Therefore, it is Vermont Yankee's position that drywell sump level indication is not appropriate for J-Vermont Yankee. The existing system, viewed as a Category 3 parameter, is adequate.

01-Fadiation Level in Radiation levels in the main steam line Circulating Primary' are continually monitored by the main Coolant' steam line' radiation monitors. A steam line isolation and scram are generated by these instruments if~the steam radiation exceeds a preset level, indicating a failure of the fuel cladding. Their intended function is to scram the reactor prior to the onset of harsh' environmental conditions.

In accordance with the methodology used in the Vermont Yankee EQ Program, these detectors, althoygh utilized for fuel failure events, are.not relied upon for LOCA or HELB events.

Once the MSIVs have closed, there is no circulating q

primery coolant in the main steam lines. Therefore, there is no longer a need to accurately monitor steam lino radiation levels.

In addition, the drywell high-range radiation monitors (which are environmentally qualified)

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f Page 10 of 18 Item HerYite Results will monitor radiation buildup within the drywell. Direct coolant radiation level assessments will be avallable from the chemical and health physics analysis via the Post-Accident Sampling System.

For the reasons stated above, it is Vermont Yankee's position that the existing instrumentation is acceptable.

013 Noble Cases and All anticipated post-accident plant 014 Vent Flow Rate effluents pass through the plant stack.

E4 Monitoring the common plant vent will.

E5 provide indication of effluent radiation E7 levels from these areas.

The stack E9 monitoring instruments cover the range required. Therefore. it is Vermont Yankee's position that separate monitoring of these parameters is not required. For Type E variables this is explicitly stated as. acceptable.

D2 Condensate Storage Regulatory Guide 1.97 requires CST level Tank Level indication from top to bottom. The existing range is 0 to 35'.

38'-3" is the overall height of the CST.

It is Vermont Yankee's position that the existing range is adequate. This is based, in part, on the fact that the portion of the CST above 36'-9" is cone shaped. Level increases above the 35' level do not relate to any significant additional volume. Furthermore, by procedures, the operator will limit the level in the CST to less than 35' to ensure overflow does not occur through the tank's vent.

DS Torus Level Variable D5 requires levet be monitored f rom " top of vent to top of Weir Wal'.".

The Vermont Yankee to'eus design does nat utilize a Weir Wall. Therefore, this parameter is not applicable.

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~D7-Drywell Atmospheric Drywell atmospheric temperature d'aplays Temperature.

O'F to 350'F, which is less than the

.40'F to 440'F range required. The accident analysis conducted to sup; ort Vermont Yankee's EQ Program indicates that the postulated drywell temperature will not exceed 350'F. Therefore, a O'F to 350*F range is appropriate for x

Vermont Yankee.

D9 MSIV Leak Control The Vermont Yankee design does not include an MSIV Leak Detection System.

Therefore, this parameter is not applicable.

4 D11 Isolation Condenser Variables D11 and D12 pertain to plants D12 System Level & Valve which utilize isolation condensers in Position-their design. Vermont Yankee does not utilize an isolation condenser.

Therefore, these variables are not applicable.

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'D13 RCIC Flow Both HPCI and RCIC flow indication is D14 HPCI Flow available to the Control Room.

Regulatory Guide 1.97 requires these two variables to be environmentally qualified. Per the Vermont Yankee EQ l

Program, these two variables do not l

experience harsh environments during the.

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small break LOCA event in which they are l

relied upon. Once the vessel has been depressurized, both HPCI and RCIC become inoperative and their flow indication is not needed. Therefore, it is Vermont Yankee's position that the existing l

equipment is acceptable.

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D15 Core Spray Flow In the EQ Program, flow indication D22 Cooling Water Flow to for these safety systems is not j

ESF System Components required.

In lica of various flows, the instrumentation that monitors the j

reactor and primary containment j

responses post-accident would be the ultimate indication of ECCS performance I

(i.e., reactor vessel level, pressure, drywell temperature, drywell pressure).

In addition, ECCS valve position information, along with ECCS pump motor running carrent (amps) indicates the l

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Page 12 of 18 Item Service Res. tits mode of operation end is far more valuable than monitoring flow.

Therefore, additional qualification or upgrading is not warranted. Vermont l

Yankee considers these parameters Category 3.

D17 SLCS Flow SLCS flow and storage tank level is D18 SLCS Storage Tank Level required by Regulatory Guide 1.97 to be environmentally qualified. Per the EQ Program and the Vermont Yankee PSAR (Section 3.8.4), this system provides a method to shut down the reactor from the full-power condition and maintain the reactor suberitical during cooldown, independent of the control rods. As such, it is not expected to be needed for plant safety following a Design Basis Accident (DBA).

Since this system is for independent backup of the control rods, it is not relied upon for accidents in which harsh environments are created. Therefore, environmental qualification of any SLC component is not warranted, although specified in Regulatory Guide 1.97.

These parameters are considered Category 3 by Vermont Yankee.

SLC pump discharge pressure is monitored rather than SLC flow. This parameter is adequate to "nform the operator that the pump is discharging fluid in a manner indicative of proper operation.

In addition, the Regulatory Guide requires the SLCS tank level be monitored from top to bottom.

For Vermont Yankee, this would require a range of 0" to 1.E2.5".

The available range is 0" to 1 7.5".

By procedures, the operator is to limit the level to 92% (approximately 122").

Should level exceed the 92% full matk, the operator would take appropriate action should p

level approach the 127.5" level. As such, monitoring level up to 132.5" is not necessary. Therefore, it is Vermont Yankee's position that the existing range is adequate.

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'D20 RHR Heat Exchanger Regulatory Guide 1.97 requires

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Outlet Temperature environmentally qualified monitoring of

.D21 Cooling Water" these two variables.- In.the Vermont-Temperature to ESF Yankee EQ Program. monitoring the RHR-

System Components heat exchanger shell and tube side outlet temperature is not relied upon.

The function of the RER heat exchangers post-accident is to remove stored and decay heat. =In lieu of the RHR heat exchanger temperature variables, monitoring the reactor and primary containment responses (i.e., torus water temperature, drywell, and reactor pressure) will be the most important indicators of RHR heat exchanger performance. Therefore, additional qualification or upgrading is not i

warranted. Vermont Yankee considers I

these parameters Category 3.

D24 Emergency Ventilation The Regulatory Guide requires that this Damper Position parameter be environmentally qualified.

However, per the Vermont Yankee Environmental Program, environmental qualification of damper position is not required. This is because the dampers are located outside the Reacter Building. As such, they will not experience a harsh environment.

Therefore, it is Vermont Yankee's position that emergency ventilation damper position is not required to be environmentally qualified to satisfy the intent of Regulatory Guide 1.97.

D25 Status of Standby Power The Regulatory Guide requires that this I

(A variable be environmentally qualified.

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thru Variables D25J, K, N, and 0 have been I, L, determined to satisfy this requirement.

and M)

The remainder of the Variable D25 indications do not require environmental qualification because none of the cables or components are located within a harsh environment. Therefore, it is Vermont Yankee's position that the remaining D25 variables are acceptable without environmental qualification.

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1. tem Service Results i

E2 Reactor Building or Post-accident secondary containment area 1

Secondary Containment radiation monitoring, as'well as Area Radiation radiation monitoring in other areas where personnel access may be desirable, would be helpful to the Health Physics Department in determining local radiological conditions prior to entering these areas. This function is important from the standpoint of evalt: sting personnel habitability in the event of a severe core damage accident.

Areas outside the Reactor Building that do require personnel access post-accident have been analyzed using very conservative assumptions to show that habitability would be allowed.

The EQ Program asstunes that habitability in the Reactor Building is not possible for at least three months post-accident. Equipment required for long-term post-accident operations has l

generally been environmentally qualified for one year. Therefore, any decisions.

on habitability inside the Reactor Building would not be necessary for some time after the event.

If the secondary containment area radiation monitors were not functioning at this time, alternate means to estimate secondary containment radiation levels would be possible (i.e., correlations based on drywell, vent stack, and site area radiation measurements).

)

l Therefore, Vermont Yankee considers this parametar Category 3.

E6 Noble Cases and Variable E6 pertains to a Reactor Shield Vent Flow (Reactor Building annulus. Vermont Yankee does Shield Annulus) not utilize a Reactor Shield Building in their design. Therefore, thic is not applicable.

7791R LL-_____--_-_

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Page 15 of

p Item Servir.g,

Resulta

'E8 Airborne Radioactive'

.These monitors are located in.the Material' Releases -

stack.--The only possible harsh Common Plant environment'is due to radiation. This

-Ventilation.

equipment is specifically designed and-l tested to measure-radiation-levels higher than those which will be encountered. Therefore, they are qualified:for their intended service.

These instruments read out in CPM and millirem; however, a. simple conversion to microcuries per. cubic centimeter can be accomplished by Health. Physics. The range of millirem, once converted..

envelopes the uCi/cc range specified by-Regulatory Guide 1.97.

Therefore, it is Vermont Yankee's position that the existing' instruments satisfy the intent of the Regulatory Guide.

E12 Environments Radiation Presently,, there is one portable survey Radioactivity Plant instrument at Vermont Yankee that can-4 R/hr. photons, but and Environments measure up to 10 Radiation none that can measure the Regulatory 4 R/hr beta.- The Guide required.10 existir.g instrumentation can measure 2 R/hr beta. These approximately-10 ranges are sufficient for portable plant use.

E16 Atmospheric Stability-The existing delta temperature is ranged

-5'F to +15'F.

Regulatory Guide 1.97 requires a range of -9'F to'+10'F.

This

~

covers all seven stability cit.sses.

It is Vermont Yankee's position that the existing range is adequate. This'is based on the fact that the existing i

range has historically been adequate over the operation of the system.

Expanding the range does not provide l

improved information.

.E17 Primary Coolant Sample Regulatory Guide 1.97 requires the (pH) on-site ability to perform several l'

different analyses on the primary l-coolant sample, one of which was a pH concentration of 1 to 13. However, in a previous Vermont Yankee letter, dated September 21, 1984, concerning NUREG-0737. Item II.B.3, " Post-Accident 7791R

1i b

Page 16 of 18 11cm Service Results l

Sampling Capability," Criterion 10, that, "... pH measurements are not included because an undiluted sample cannot be obtained from the post-accident sample panel." The NRC issued a safety evaluation report on January 14, 1985 accepting this position. The above exception is based on tests conducted at Vermont Yankee on actual reactor coolant samples. This sample was obtained and diluted with demineralized water to a dilution of 1000:1, which is the minimum dilution 1

appropriate to maintain personnel radiation exposures ALARA for the expected post-accident coolant activity levels. The resulting measurement concluded that no meaningful information was obtained other than the undiluted sample was acidic or alkaline.

Additionally, Vermont Yankee evaluated the need to measure coolant pH at a freshwater BWR site and determined that pH is not particularly important since all metals which contact the crolant are compatible with liquids having a wide range of pH.

Thus, we conclude that relatively little meaningful information would be gained from post-accident coolant pH sampling.

Therefore, based on Vermont Yankee's prior notification to NRC stating that undiluted pH samples cannot be obtained for the post-accident sample station; NRC's accepbmce of Vermont Yankee's provisions'to meet NUREG-0737, Item II.B.3, Criterion 10; and Verment Yankee's evaluation of diluted pH samples discussed above, we have removed primary coolant pH from our post-accident monitoring instrumentation list.

7791R

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.-Page.17.of;18 i

3.- ' Instrumentation Requirine Upgrade _or Modification:

'This section details additional instrumentation needed for compliance ~to

,the' Regulatory Guides, This additional instrumentation consists of.any1

~

equipnent which requires modifications to establish compliance. This

could consist: of. entirely new. instrument channels.,or existing instrument g..

. channels which require some upgrade.

.;r

-There are presently no parameters which require upgradinF.

1

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k Page 18 of 18 d:

4.

Instrumentation Deleted from the Submittal This section details instrumentation which has been deleted from the original Regulatory Guide 1.97 submittal. The equipment removed and the reasons for the removal are listed below:

Ilta Service Resulta A3 Reactor Vessel Originally, Vermont Yankee clacuified Reference Leg Area this variable as Type A, Category 1, Thermocouple based on the Vermont Yankee draft Emergency Operating Procedures (EOPs).

Vermont Yankee has further developed the E0Ps and concluded that these variables I

are not Type A variables. This is based on the fact that this variable does not provide primary indication of a plant parameter. The reference leg thermocouple provide the Control Room operators with information on the reliability of the reactor vessel level indication. As such, they provide indication of the confidence in a variable providing primary indication of a plant parameter. Based on the above discussion, Vermont Yankee has et, coved this item from the Regulatory Guide 1.97 submittal. However, reference leg thermocouple will be installed as a part of the resolution of Generic Letter 84-23, " Reactor Vessel Water Level Instrumentation of BWRs."

B10 Primary Containment RHR shutdown cooling supply, Valve 10-18 (Valve Isolation Valve has been removed from the original 10-18) Position Regulatory Guide 1.97 submittal and the Vermont Yankee EQ Program.

This valve is normally closed by a pressure interlock during plant operation and opened only when the plant is shut down. Following a LOCA, this valve is not needed for accident mitigation.

Additionally, post-LOCA failure will not cause the valve to open.

Consequently, removal of this valve from the Regulatory Guide CIS valve position list is acceptable.

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ML20246M636

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