ML20214D858

Forwards Proposed Changes to Next Rev to FSAR Amend 18

ML20214D858
Person / Time
Site:	Beaver Valley
Issue date:	05/15/1987
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-123, TAC-65611, NUDOCS 8705210511
Download: ML20214D858 (28)

Text

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2NRC-7-123 (412)393-7546 Beaver Valley No. 2 Unit Project Organization Telecopy (412) 393-7889 QG j' "

May 15, 1987 B

Shippingport. PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

Beaver Valley Power Station Unit No. 2 Docket No. 50-412 FSAR Amendment 18 Changes Gentlemen:

Attached is a copy of changes which are currently expected to occur in the next revision to the Beaver Valley Unit 2 FSAR, Amendment No.18.

The formal FSAR Amendment will be the same or very similar to the attached copy.

If ycu should have any questions, please call Mr. R.

W. Roth at (412) 643-5200, Extension 154.

DUQUESNE LIGHT COMPANY

/

By

'o V. J' Carey Senior Vice President RWR/ijr NR/RWR/AMND/18 Attachments AR/NAR cc:

Mr. P. Tam, Project Manager (w/a)

Mr. J. Beall, NRC Sr. Resident Inspector (w/a)

Mr. L. Prividy, NRC Resident Inspector (w/a)

Mr. William T. Russell, NRC Region I Administrator (w/a)

INP0 Records Center (w/o/a) 8705210511 870515 0 l PDR ADOCK 05000412 k

K PDR I

United States Nuclear Regulatory Commission FSAR Amendment 18 Changes Page 2

~

COMMONWEALTH OF PENNSYLVANIA.)

)

SS:

- COUNTY OF BEAVER

)

On this /

day of M

, /[N

, before me, a Notary Public in and for said Commonhealth and County, personally appeared J.

J. Carey, who being duly sworn, deposed and said that -(l) he is Senior Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth J

in the Submittal are true and correct to the.best of his knowledge.

Ol/?

Notary Public MULA S. FAffettE. NOTATY PLGttC 36IPPIEPORT 005, SEAMR WUtE ENEllI433400 EIPitES SCf. 23,130t i

W Pm:.%=de Associeties of Betwis 1

e,-

EVPS-2 FSAR TABLE 1.3-2 (Cont)

FSAR Section

/PSAR Reference Significant Changes Since'PSAR accommodate cold shutdown.

10.3.2 11ain steam supply system changes include:

/10.3.1.2 1.

Replaced nonreturn valves with main steam isolation valves to prevent reverse flow of fogg h M steam in event of accidental pressure reduction.

]

Nh Dr.

,2.

liain steam line trip valves changed from J

' swing disk-type to hydraulically-operated 4/

p

[

ball type, held open by solenoid-cperated k ^m 3 N mechanical latch.

d W.

k 3.

Parallel trip valve configuration for turbine-driven auxi_iary feedwater pump steam supply changed.

Presently, three pairs of series solenoid-operated trip valves are

provided, one pair in each of the three 3-inch lines between the 32-inch main steam line and the 3-inch turbine drive common header.

P 10.4.4 Added cooling tower pumps and low-low Tavg

/10.3.1 permissive interlocks to turbine bypass control,

valves capabilities.

10.4.5 Circulating water system changes include

/10.3.4 1.

Total dynamic head of cooling tower pumps reduced from 96.4 feet to 73 feet through use of natural draft counter-flow cooling tower with its lesser static lift requirements.

2.

Addition of flood indicators to valve pits on suction side of cooling tower pumps, inlet and outlet sides of condenser, and turbine building retention pit, all with flood alarms to main control room.

10.4.6 Addressed new condensate cleanup

system, a

/lione IMS class system, consisting of two subsystems, condensate polishing system and powdered resin dewatering system.

4 10.4.7.2 Changes to condensate and feedwater. systems

/10.3.5 include:

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LOGIC DIAGR AM STEAM GENERATOR

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BVPS-2 FSAR The performance requirements of the MSSS are shown on the heat belance diagram, Figure 10.1-1, with the design and performance characteristics shown in Table 10.1-1.

The MSSS is designed for 1,100 psia and 560 F, and the environmental design criteria is specified in Section 3.11 for the Class 1E components.

10.3.2 Description Steam from each of the three steam generators passes through 32-inch outside diameter (OD) carbon steel pipes.

A steam flow meter, interconnected with a three-element feedwater _ control system, is provided in the main steamline at the outlet of each steam generator.

A MSIV in each of the three main steamlines is lecated in the main steam valve house, immediately outside the reactor containment.

Following the MSIVs, the three main steamlines enter a single, 38-i inch OD manifcid.

Connections for the turbine steam bypass, turbine l

steam sealing system, reheater supply, and auxiliary stcam supply are provided at the manifold.

From this manifold, steam passes to the turbine step trip valves and governor valves.

The MSIVs autcmatically prevent reverse flow of steam in case of accidental pressure reduction in any steam generator or its piping.

If a steamline breaks between a MSIV and a steam generator, the affected steam generator continues to blow down while the isolation valve prevents blowdoun from-the other steam generator.

In addition, the MSIVs prevent blowdown through a ruptured pipe downstream of the isolation valves.

This steamline break accident is discussed in 1

(hhhtiGL,s4E'TN96 Pr*(.umM ICCBAN The 63Ti-d MSIVs are opened

~ 3 and are held cpen by vor-

~::F._____.-

If a pipe ruptures either upstream or downstream of an isolation valve a ma'n steamline isolation sional causes.a.

V(e<t

.eep solenoidsto release D

.in.1 I nch, closing the valve by spring force.

Maximum closing time for the isolation valve upon receipt of the signal is 5 seconds.

Valve closure prevents rapid r

cooling of the RCS by limiting SGS to a single steam generator.

Isolation valve closure also ensures a supply of steam for the l

turbine-driven steam generator auxiliary feedwater pump.

j

~ fts.WgrX 4 Five ASME Code Section III steamline outside the contaiprgnt_and_ups,tream Q thesafety valves ar MSIVs. CT'hese gav V safe valves re ' sized to pass the steam Ilow,resul1!ing from a i complete oad rejection, or other shutoff of main steam flow, without a direct reactor trip.

The maximam capacity of any single safety valve does not exceed 890,000 lb/hr at 1,100 psia, thus limiting SGB if a single valve sticks cpen.

p

(

v

~

s l

Excess steam generated by the sensible heat in the nuclear steam

'n supply system immediately following loss of load is bypassed cirectly to the turbine cendenser (Section 10.4.1) by means of two turbine

\\

steam bjpass lines (Section 10.4.4), which provide a total bypass capacity of 90 percent of full load steam flow.

Amendment 3-1 10.3-3 Octcber 1983 fQ s!2.sl fthAY/fC/A $@'<Y'( MYW (J \\

BVPS-2 FSAR 4

prevents rapid cooling of the RCS.

The llSIV closure also ensures a supply of steam to the turbine-driven auxiliary feed pump.

Single failure of a !!sIV is discussed in Section 15.1.S.

Further discussion of main steam system component failure can be found in Sections 15.1 and 15.2.

If a main steamline breaks between a !!SIV and a steam generator, only that steam generator vill blow down.

Closure of the 11SIV in the.

ruptured line prevents blowdown from the other steam generators.

The maximum capacity of any single main steam safety valve, steam bypass valve. residual heat release valve or atmospheric dump valve does not exceed 890,000 lb/hr at 1,100 psia inlet pressure.

This feature limits the potential uncontrolled blowdown flow rate in the a valve inadvertently fails or sticks in the open position.

To event prevent a postulated large steam flow blowdown from more than one steam generator due to the valve failing or sticking open the residual heat release valve is normally aligned to only one steam generator. However, the valve can be aligned to any one of the three steam generators.

Failure modes and effects analyses (FHEA) to determine if the instrumentation and centrol and electrical portions meet the single failure criterion, and to demonstrate and verify how the General Design Criteria and IEEE Standard 279-1971 requirements are satisfied, have been performed on the main steamline isolation system. The FHEA methodology is discussed in Section 7.3.2.

The results of these analyses can be found in the separate FHEA document (Section 1.7).

10.3.4 Inspection and Testing Requirements Piping and equipment of the USSS designed ^as Seismic Category I require preoperational and periodic in-service testing.

For discussion on preoperational

tests, refer to Chapter 14.

Section 3.9B.6.2 discusses in-service tests of valves.

In-service tests of other Class 2 and Class 3 components are discussed in Section 6.6.

Test requirements of the HSIVs in the USSS are as follows:

Prior to service, each IISIV shall be cycled from fully open to fully closed.

This cycling will cccur with cold and hot system conditions.

During cold system condition tests (i.e., no elevated pressure or temperature), the 11SIV nca mai causur e and' trip closure time will

'i rame be checked.

The inservice closure capability will be_ verified (i.e-l0' percent closureFomo f or each opening cycle the(nycto m g N stem >

y

\\ pressure will be monitoredj Limit switch operation ano indicating lights will also ce cnecneo for operability.

During hot system condition (no load pressure and temperature),

each MSIV will be closed by a trip signal frc.a Train "A," then closed by a trip signal Amendment 12 10.3-6 June 1986

BVPS-2 FSAR m\\\\ b4 mgacMD generated from Train "B."

For each trip cycle the closure time f

• A D88-ma -, m, =r c

c+n-n-acenre i eoou eu w

vorenu wui n

n i t oi eig 4

c Amendment 12 10.3-6a June 1986

j BVPS-2 FSAR other 95 percent has a partition factor of.0.01.

In.the air ejector, c4-the partition factor is 0.15 for the volatile 5 percent of the iodine and 0- for the nonvolatile 95 percent of the iodine.

10.3.6-Steam and Feedwater llaterials The typical material specifications used in-the code class 2 and 4

i

~ Class 3 main. steam and feedwater piping systems are listed in

• l Table 10.3-2.

The materials used for the code Class 2 portions of the steam generators are discussed in Section 5.4.2.1.

10. 3. 6'.1 ' Fracture Toughness Fracture toughness testing of Code Class 2 and Class 3 components was optional in the editions of the ASME Code Section III.in effect.at the time of. procurement fot BVPS-2.

Due to successful power plant operating experie.

s with the materials.of construction, fracture 4

toughness testing was not generally specified for the main steam and feedwater system piping and components.

Fracture toughness testing was specified, however, for the weld filler metal used in the field erection of piping. Tes:ing is to the requirements of ASME Code j

Section III, HB 2400, and the applicable ASME Code Section II, j

Part C, filler material specification.

In addition, where components 1

were fabricated to later editions of ASHE Code Section III that J

required fracture tougnness testing, this testing was performed in accordance with the code then in effect.

i 10.3.6.2 Haterial Selection and Fabrication i

l The pressure retaining materials specified for use in the Code' 4

Class 2 and Class 3 main steam and feedwater systems conform to Appendix I of ASME Code Section.III, and to' Parts A, B, and C of AS!!E l

Code Section II.

Compliance to Regulclory Guides 1.31, 1.36, 1.44, 1.50, and 1.85 is discussed in Section 1-8.

Welding in areas of limited welder accessibility is controlled, as applicable to the materials of construction, per Regulatory Guide 1.71, as discussed in

]

Section 1.S.

Cleaning of Code Class 2 and Class 3 main. steam and feedwater systems is controlled in accordance with ANSI H45.2.1, per j

Regulatory Guide 1.37, as discussed in Section 1.8, Hondestructive examination of tubular products was specified in accordance with ASME 1

Code Section III.

The allowable' design stresses for' tubular products are consistent with the degree of nondestructive testing, as required.

4 by ASME Code Section III.

4 s

10.3.7 Ins.trumentation Requirements Control switches with indicating lights are provided in the main i

control room for the llSIVs.

These valves have-an extra set of l

indicating lights located on the !!SIV ' logic cabinet.

These !!SIVs require electric power for opening, which is done W P O

1. g4 j

They will close upon signal actuation-by mechanical spring force.

l These valves are cpened manually provided a main steamline isolation Amendment 2 10.3-8 July 1983 4

.-.-.._...,.,.,-.m

__.,..mm.

__m.,,

BVPS-2 FSAR B7.0

~

~

signal Train A or Train B is not present.

These trip valves will close provided a ma_in steamline isolation signal from either train exists. Qcegencv T1osure of'tTie TiSTVs will be at a f aster rate th closure _.f' N- _

~

C-Testing capabilities are available at the MSIV logic cabinet for the MSIVs.

Fushbuttons are provided on the logic cabinet for performing these test procedures, which consist of closing and epening of these 4

g trip valves.

v g

A white statiis indicating liglit'3TiF6vided on the llSIV logic cab'inet for indicatina that testina is in progress.

yx

/

Control switches with indicating lights are provided in the main control roem for the main steamline bypass trip valves.

An extra control switch with indicating lights is provided in the main control room for each bypass trip valve. These valves are cpened manually.

The valves will close when they receive a main steamline isolation signal, Train A or Train B.

Annunciation with associated computer inputs is provided in the main control room for the steamline stop valve not fully cpen and bypass valve not fully closed.

Status indicating lights are provided on the !!SIV logic cabinets for emergency trips of channels A and B, solenoid valves open, solenoid valves closed, and both trips available.

Pushbuttons are provided in the main control room for manual initiation of the steamline isolation signal.

This <ignal will be initiated automatically when a high rate of change of steamline pressure (detected in two out of three channels) of any steamline is present and steamline isolation / safety injection is blocked, Hi-2 reactor containment pressure detected in two out of three. channels or any steamline pressure low (detected in two out of three channels),

either hot or cold leg isolation valve is open, and steamline isolation / safety injection signal is not blocked.

Pushbuttons are provided at the emergency shutdown panel (ESP), which will transfer control to the ESP for the steamline/ safety injection block reset.

A manual reset pushbutton is used to transfer control back to the main control room.

Annunciation with associated computer inputs is provided in the main control room for: loop A steamline high rate of pressure change for l

channels II,

III, and IV; loop B steamline high rate of pressure change for channels II, III, and IV; loop C steamline high rate of pressure change for channels II,

III, and IV; one out of three steamline high rate of pressure change, containment pressure high/high-high for channels II, III, IV; loop A steamline pressure low for channels II, III, and IV; loop B steamline pressure low for Amendment 9 10.3-9 December 1984

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i TASIA 7.5-1 SAFETY RELATED DISPLAY 1hSTRUMENTATION (SEE NOTES 1,2,3)

Qaalification haber hdicator Implementation Ib me r Variable Rang e/ St a t us Type / Category Environmental Seinste of Channels laevice Date (t))

g Conformance i

RCS pressure (WR) 0-3,000 pois AI, Bl. Cl, 32 Ye s Ye s 3 per plant 2 antere fuel load IE in s C2, D2 I channel on plasma display I recorder RCS Tgg (WR) 0-700

• F AI, 32 Yes Yan I per loop 3 meters fuel load IE Yes j

3 recorders s

RCS Teold @)

F Al, B2 Yes Yes 1 per loop 3 meters fuel load IE Yes 3 recorders Steam generator 0-10E of span AI, 51, 32, D2 Yes Yes 1 per steam 3 meters complete LE Yes level (hb generator 3 recorders Steam generator 0-Iom of span Al, 81, D2 Yes Yes 3 per steam 9 meters fust load it Yes level (UE) generator 3 recorders Pressortser level 0-102 of span AI, BI, D2 Yes Yes 3 per plant 3 meters complete IE Yes 3 recordera Conta1 ament pressure

-5 to 55 pesa a l, 31, 3 2. C2, Yes Yes 4 per plaat 4 meters k

D2 c9pleta IE Yes 2 recorders Steam 11ae pressure O to I,200 AI, Bl. D2 Yes(84)

Yes 3 per loop 9 meters comple ta IE Yes 1

pois 3 recorders containment water 0-225 in Al, Sl 82, C2, Yes Yes 2 per plant 2 meters complete IE Yes level (WR)

D2 i recorder Containment water 0-12 la AI, 31, 52, C2, Yes Yes 2 per plant 2 meters fuel load IE Yes level (WR)

D2 1 recorder Q

nefuelig water 0-73) in D2 Yes Yes 2 per plant 2 meters completa IE Yes

]

storage taak level l

I recorder Amen h et 16 i ef !!

A ril 1982 P

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RVPS-2 FSAR TABLE 7.5-1 gnatification Variable Ranc.e/ Status Type /cate+>ry Environmental Ofseic of channels Device Date (IM Supply conformance I

Number InJ1cator leptementation Power Reactor vessel level Instrumentation system Full range 0-1202 level 32 C2 Yes Yes 2 per plant 2 channels on fuel load LE No(5) plases display; i

I channel on i

Upper range 0-120% level 32 C2 Yes Yes 2 per plant 2 channels on fuel load IE No(5) recorder plasma display; I channel on Dynaete head 0-120% liquid 52, C2 Yes Yes 2 per plant 2 channels on fuel load IE No(5) recorder plasma display; I channel on I

recorder I

! ).

+

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b I

l Aa-efern t il 2a of il 9

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i BVPS-2 FSAR i

j TuLE 7.5-3 (Cont) tjualification Numhe. r Indicator Implementation Power Vartable Range / Status Type / Category Fnvironmental Selsmic of Channels Device Date (ll)

Supply Conforeance Containment hydrogen 0-30%

Bl. Cl Yes Yes 2 per plant 2 channels on fuel load IE Yes concent ret t on plases display I channel on recorder Plant vent 10' -10 pct /cc C2, E2 Yes Yes I per plant I meter fuse load IE Yes radiation level I recorder Containment isola-Open/ Closed C2, D2 Yes(12)

Yes(12)

I per valve' I pair lights complete IE(II) tion valves status Yes per valve containment pressure 0-180 psta C1, C2 Yes Yes 2 per plant 2 channels on complete IE Yes (eatended range) plasma display I channel on recorder Primary coolant lyct /ml to C1 No M/A Analysis complete not.-lE Yes activity 10 ct/mi V

Site enviros, ental C1, El h

No N/A Portable complete l

non-lE Yes radiation level

• j 1

Psessurizer heater CloseJ-trip D2 Yes Yes I per heater i pair lights complete IE No(6) power availability per heater PotV status Open/ closed D2 Yes Yes I per valve I pair lights complete IE Yes per vtive Charging system 0-150 gym D2 Yes Yes 1 per plant I meter complete non-lE Yes l

flow 1

Primary safety Open/Cioned D4 Yes Yes I per valve plasma display fuel load IE Yes valve states Letdown flaw 0-200 gra D2 Yes Yes 1 per plant I meter complete non-lE Yes Volume control 0-100% of span 02 Yes Ye, I per plant I meter complete non-lE Yes tank level CVCS valve status open/ Closed D2 Yes Yes I per valva I pair lights complete IE Yes per valve Amendment il 3 of II January 19H6

~._.. _.. _

4

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i i

j BVPS-2 FSAR Taalz 7.5-8 1

SAFETY RELATED DISPLAY INSTRUNENT*T11al (SEE nurES 1,2,3)

,)

Qaa11tication haaber Indicator hplementation abwe r variable sanae/ Status Type / Catesory Environmental Setanic of CImannels Device Date (13) g Conformance t

RCS pressure (WR) 0-3,000 pois A1 St. Cl, 52, he ile s 3 per plant 2.anters fuel load IE he C2, D2 1 cheeeel on plasma dispisy I recorder RCS Tgg (WR) 0-700'F Al, 52 Yes Yes

! per loop 3 meters fuel load IE Yes t

3 recorders

(

RCS T,,gg ( W

&WF Al, 82 Yes Yu 1 per loop 3 meters -

fuel I W IE

. Ye s 3 recorders

{

Steam generator 0-10E of span AI, si, 52, D2 Yes Yes '

! per steam 3 meters emplete IE Yes level (ba.,

generator 3 recorders i~

Steam generator 0-10E of eran A1, 58. D2 Yes les 3 per steam 9 meters fuel los*

LE Yes level (WR) generator 3 recorders j

Fressuriser level 0-10E of spa A!, 51. D2 Yes Yes 3 per plant 3 metere complete 1E Yes 3 recorders j

Coatstament pressure

-S to 55 pela AI, Bl. s2, C2, Yes Yes 4 per plant 4 meters k

i D2 c9plete IE Yes 2 recorders i

Steamline pressure.

O to 1,200

. AI, s!, D2 Yes(14)

Yes 3 per loop 9 meters complete IK Yes 1

l peig 3 recordere j~

Coetainment water 0-225 to A1, SI, s2, C2, Yes Yes 2 per plant 2 meters complete IK Yes j

level (WR)

D2 4 recorder i

Coatsimment water 0-12 la AI, SI, 82, C2, Yes Yes 2 per plass 2 meters fuel load IE Yes i

level (WR)

D2 i

1 recorder j.

aetmettes unter 0-73) la D2 y.

I*'

2 per plant 2 meters complete Ig y,,

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storage tank level n

I recorder <

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, Amen h am 16 L

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j April 1987 i

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I avrs-2 rSAa i

TABLE 7.5-4 (Cont)

Qualification Number Indicator Implementation Power Variable Range /Statua Type / Category Environmental Seismic of Channels Device Date (13)

Supply Conformance Primary riant 0-350 in Al, D2 Yes Yes 3 per plant 2 asters fuel load IE Yes DWST level I channel on plasma display I recorder Aust11ary feeduster 0-400 spa Al Et, D2 Yes Yes 2 per loop 6 meters fuel load I E, Yes flow 3 recorders Core exit 100-2200*F Al, 31. C1 Yes Yes 51 All channels on fuel load it Yes temperature plasma display; l

I channel on meter and recorder 7

Containment area 10*-10 FJHr Al, St. 52. E2 Yes (/[

Yes 2 per plaat 2 meters fdelload radiation 4.*.*1 IE Yes (high range) 2 recorders 3

Secondary systes 10~ -10 W1/CC A1, 82, E2 Yes Yes 1 per loop 1 aster fuel load IE Yes l

radiattoa 1 recorder i

RCS subcooling 200*F sub-A?, 32 Yes Yes 2 per plant 2 channels on fu load IE Yes cooling to 35'F super-plasse display; I channel on meter bested and recorder 1

Control rod Im/Out 53 No No 1/ rod I status complete non-lE Yes posittoa light / rod Neutron flus 6

louer range I to 10 CPS 54 Yes Yes 2 per plaat 2 cbsanels on fuel load IE Yes pleses display; I chac ul on recorde r Upper range 0-2002 of power 31 Yes Yes 2 per plaat 2 chamas? on fuel load IE Yes plasma a* splay; I channel on on reco-<tr Amendment 13 2 of II January 1987 O

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l BVPS-2 FSAR T481.E 7.5-8

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variable Range / Status Type /Ca t ego ry Environmental hismic of Channels Device hate (l3)

Su ppl y conformance No*ber Indicator Implementation Pouer Reactor vessel level lastrumentatton systee i

Fett range

& l20Z 1evel B2, C2 Yes Yes 2 per plant 2 channels on fuel load IE No(5)

{

plases display; I channet on Upper range 0-12i1% level s2. C2 Yes Y es 2 per plant 2 channels on fuel load IE No(5) recorder plasma d(aplay; I channel on Dynaete head 0-1203 tiquid 82, C2 Yes Yes 2 per plant 2 channels on fuel load it No(5) recorder plasma display; I channel on recorder I

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24 uf 11

.Saou.4 r y 19n.

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l BVPS-2 FSAR T4 ALE 7.5-8 (Cent)

<bsaltftention Numtwr Indicator implementation Power Verla g Ran, e/S t at us Type / Category Favironmental

$#tsnic of Channels Device Date (13)

Supply conformance Containment hydrogen 0-10%

SI. Cl Yes Yes 2 per plant 2 channele on fuel Inad IE Yes concentration plasma display I channel or, recorder plant vent 10~ -10 pct /cc C2, E2 Yes Yes I per plant I meter fuel load IE Yes sadiation level I recorder Containment Isole-Open/ Closed C2, D2 Yes(12)

Yes(12)

I per valve',

I pair lights complete IE II) tion valves *tates Yes per valve Containneet pressure 0-180 psia C1. C2 Yes Yes 2 per plant 2 channels on complete IE Yes (estended range) plasma display I channel on recorder Primary coolant luct/ml to C3 No 3/A Analysts complete non-4E Yes activity 10 et/ml Site environmental C3, E3 No No N/A Portable eneplete non-lE Yes radiattoa level

'4 1

Pressertaer heater CleseJ-trip 02 Yes Yes I per heater I pair lights complete IE No(6) power availability per heater PORW status open/ closed D7 Yes Yes I per valve I pair lights complete IE Yes per valve Charging syste.

0-150 gym 02 Yes Yes I per plant I meter complete non-IE Yes flow r=*sary safety open/ Closed D2 Yes Yes I per valve plasma display fuel load IE Yes valve status Letdown flow 0-200 gym D2 Yes Yes I peu plant I meter complete non-lE Yes Velume contro!

0-100% of span D2 Yes Yes I per plant I meter complete non-lE Yes tank level CWC5 valve states open/ Closed D2 Yes Yes I per valve I pair lights complete IE Yes per valve AmenJernt il 3 of II January 19%

r l

l SVPS-2 FsAR TARLE 7.5-l (Cont)

Variable Range /S t 4 t us Type / Category Favtronmental Seismic _

of Channels Device hate (13)

Sopply Conformance Qualtitention Blunbe r Indicator Implementation Power Decay heat remosal Open/elosed D2 Yes Yes I per valve 1 patt lights complete IE Yes valve status per valve his steaali.w open/ closed B2, D2 Yes Yes I per valve I pair lights complete SE Yes toolation valve status per valve hin steamlame Open/ closed 82, D2 Yes Yes I p.tr valve I pair lights complete LE Yes isolation valve volve per valve S/C safety valve Open/.losed D2 Yes Yes I per valve plasma display fuel load IE Yes status RCP seal injection 0-15 spe D2 Yes Yes I per pump 3 meters complete non-lE Yes flow S/G ateuspherte opeg/ closed 02 stema dump valve Yes Yes I per valve I pair lights complete it Yes status per valve Nin feeJwater con-Open/ closed D2 Yes Yes I per valve I pair Itghts complete IE Yes trol valve status per valve his feedwater Opea/ closed D2 control bypass Yes Yes I per valve I pair lights

complett, IE Yes valve status per valve him feedwater Open/ closed D2 Yes Yes I per valve I petr lights completh' IE Yes toelation valve

.s Ctstes per valve Mata feedwater flow O-5 HPrat 02 Yes Yes 2 per Sit.

6 meters complete IE Yes S/G blowdown isola-Open/ closed D2 Yes Yes I per valve I pair lights complete it Yes tion valves status per valve attist flow 0-1,000 spo D2 Yes Yes I per train 2 meters complete IE Yes AmenJeant II 4 of II January 1986 o

O O

O*.

V(~%

,/ N

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AVPS-2 FSApt TABl.E 7.5-l (Cont )

tjual i f icat tan Numbe r Indicator Implementation Power Variable

_R.enfe /S t it us Type /Ca t ego rv Environmental Selseir of Channels Device Date (51)

Supply Conformance LHSi flow O-5,IMH) gpa D2 Yes Yes I per train 2 meters complete non-l E

• Yes F.CCS valve status Open/ closed D2 Yes Yes I per valve I pair !!ghts complete IE Yes per valve Aust!!ary feedwater Open/ Closed D2 Yes Yes I per valve I pair lights complete IE Yes valve status per valve Containment spray 0-180%

D2 Yes Yes I per pump 4 meters complete IE Yes flow Containment spray Open/ closed D2 Yes Yes I per valve I pair lights complete IE Yes system valve status per valve CCW header 0-150 psig D2 Yes Yes I per header 3 channels on corsplete IE Yes pressure plasma display CCW header 0-200'F D2 Yes Yes I per header 3 channels on complet-lE Yes temperature plasma display CCW surge t.stik 0-70 in D2 Yes Yes I per tank 2 meters level complet e $'

IE Tea I

CCW flow 0-1,000 gpm D2 Yes Yes I per header 2 meters complete tg Yes CCW valve status Open/ closed D2 Yes Yes I per valve i pair lights complete IE Yes per valve Service water Open/ closed D2 Yes Yes I per valve I pair lights complete IE Yes system valve statug per valve Service water 0-150 psig D2 Yes Yes I per train 2 meters complete IE Yes system pressure HVAC Open/ closed D2 Yes Yes

! per deeper i pair lights complete IE Yes per damper AmenJ= nt il 4 of Il

.fanuary 19%

RVPS-2 FSAR TABl.E 1.5-4 (Cont) qualtfteattan hoher indleator laplementatton Power Vertahle Range /St at us Type / Category Environmental Setsmic of Channels Device Date (I3)

Supply Conformance Ac/de, vital Bus specific D2 Yes Yes I per hus I per bus complete IE Yes in st rument voltage RHR heat exchanger 50-400 *P D2 Yes Yes

! per he.at 2 meters complete non-lE Yes discharge temperature exchanger RHR flow 0-5,000 gpa D2 Yes Yes 1 per train 2 meters complete IE ~

Yes MHR valve status Open/ closed D2 Yes Yes I per valve I pair lights complete IE Yes per valve Reactor trip Close-trip D2 Yes Yes I per breaker Computer complete IE breaker position yes Turbine stop 0-100%

02 No No 1 per valve 4 meters complete non-lE Yes valve posit ton Turbinethshtte 0-100%

D2 No No I per valve 4 meters complete non-lE Yes valve position Ntor driven Run-trip D2 Yes Yes I per pump i pair lights complete IE Yes aust!!ary feedwater pump status per pump Turbine driven Open/ closed b2 Yes Yes 1 per steam I pair of completli IE aus t !!a ry f eedwat e r 1) water pump status adelssion lights per yes valve valve

{

Safety injection Run-trip D2 Yes Yes 1 per pump 1 pair lights complete SE Yes pump status per pump Service water Run-trip D2 Yes Tes I per pump I pair lights complete IE Yes pump status per pump CCW pump status Run-trip D2 Yes Yes I per pump I pair lights complete IE Yes per pump Amendment il 6 of Il January 1986 S

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9

-. ~

_ -. -. ~ - -. - _. _. _

-... _ _., ~. -. - - -.

. ~.

m BVPS-2 FSAR TABLE 7.5-1 (cont)

Qualtitcation Numtwe r Indicator laplementation Power Variable Range / Status Type / Category Environmental Seismic of Channels Device Date (13)

Supply Conformance Control room 10-2-103 er/hr E2 Yes Yes 2 per plant 2 seters fuel load IE Yes radiation 2 recorders I

Service water to 10 -10 pct /sc E2 Yes Yes I per pathway I per pathway fuel load IE

• Yes rectreulation heat exchanger concen-tration from liquid pathways Plant vent air 0 to 75.000 E2 Yes Yes 2

2 meters complete IE Yes flow rate SFOt Meteorlogical parameter E3 No No I

strip chart fuel load non-!E-No(7) parametera spec 1fIc recorder Condenser air ejector radiation Air ejector 10

-10'I pct /cc E3 No No one per vent one per vent fuel load

• non-!E Yes discharge

-6

-l

$l Air ejector delay 10 -10 pct /cc E3 No No one per vent one per vent fuel 1 mad non-lE Yes bad exhaust SI accumulator 1 I tank level No(8)

SI tres. pressure No(8)

SI accumulator isolation valve Yes(8) status horic acid charging flow No(9)

Amendment 12 7 of 11 June 1986

eVPS-2 FSAd TAB 12 1.5-1 (Cont)

Qualification haber Indicator Implementation Power Variable Range / Status TYPE /Categorv Environmental Setssic of Channels Device Date (13)

Supply Conformance RCS soluole buron 50-6000 ppe BJ h

No 1

I per channel fuel load non-lE Yes concentration Anal ais of primary 1sotopic E3 N/A N/A I

analysis fuel load non-lE Yes f

coolant (gamma analysis spectrue)

Primary coolant parameter E3 No No 1

I per channel fuel load n'on-16 '

and sump sample specific Yes Containment air pa'ameter E3 to No 1

I per channel suel load non-!c Yes sample specific l

Containment atmas-l phere temperature ho(lu)

Containment sump water temperature No(!!)

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8 Aarndment y 8 of Il December 19a4 l

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G

BVPS-2 FSAR NOTES TO TABLE 7.5-1

(-)

('

1.

Quality Assurance is in accordance with the BVPS-2 program defined in FSAR Chapter 17.

2.

EOF and TSC indications of the BVPS-2 Post Accident Monitoring Instrumentati,on will be addressed in the TSC and EOF submittals.

3.

The BVPS-2 Design Basis only identified the key variables that are used for monitoring the performance of safety systems and other systems normally employed for attaining a safe shutdown condition.

In accordance with the definitions in the Design

Basis, these variables are designated, Type D, Category 2.

The preferred backup variables to the YypeeD variables are not specified in this document.- Since these variables are designated Type D, Category 3, the instrumentation is only required to be high quality commercial grade without any post-accident environmental qualification.

A decision was made not to specifically identify the potential long list of instrumentation available at BVPS-2 that meets this definition.

Indeed, if the list was generated, it would be much more inclusive than the variables identified in Reg. Guide 1.97, Revision 2.

4.

The installed equipment is a standard Westinghouse Nuclear Instrumentation system, powered from a battery backed Class 1E Power Source.

The equipment contains isolated monitoring channels which cover the range required to be monitored.

The

(N equipment is suitable for normal operation, and the qualified

(_,)

instrument rack portion is installed in the control room which is an accessible and controlled mild environment.

Currently, no sensors are commercially available with post-accident environmental qualification; therefore, no implementation schedule can be provided at this time.

Borating the primary system after an accident in accordance with the EOPs ensures that adequate shutdown margin is maintained.

5.

BVPS-2 is installing the Westinghouse differential pressure Reactor Vessel Level Instrumentation System (RVLIS). This is an acceptable system for measuring coolant level in the reactor according to Generic Letter 82-28.

BVPS-2 uses Core Exit Temperature and RCS Subcooling to support operation according to the Westinghouse Owners Group Emergency Response Guidelines.

These guidelines require that the RVLIS meets Regulatory Guide 1.97 Category 2 criteria only. Operator verification of flows during safety injection operation and stringent termination criteria preclude the need for RVLIS under design basis accidents.

6.

Pressurizer Heater Status Regulatory Guide 1.97, Rev. 2, spe..fied that heater current was the preferred parameter for determining heater status. For BVPS-2 heater breaker position,

(}

Amendment 5 of 11 s_-

February 1984

BUPS-2 FSAR NOTES TO TABLE 7.5-1 (Cont)

O not current indication, was selected for determining pressurizer heater status due to hardware considerations. Breaker position provides adequate indication to the operator to ensure the pressurizer heaters are op,erable.

7.

The recommended ranges for this instrumentation are Wind speed 0 to 67 and -9 to 18'F for estimation of atmospheric stability.

The instrumentation to be installed will cover the following ranges: Wind speed 0 to 50 mph and estimation of atmospheric stability T (150-35 ft)

-4.0 to

+8.0'F: (500-35 ft) -6.0 to

+12.0*F.

The instrumentation fosp. rind speed meets the guidance of Regulatory Guide 1.23.

The vertical temperature ranges cover the range of lapse rates (change of temperature with height) guidance of Reg. Guide 1.23 required to estimate the atmospheric stability class.

8.

The licensing basis used in the BVPS-2 Regulatory Guide 1.97, Revision 2 Design Document was that a safe shutdown condition was a hot standby condition.

Parameters necessary to monitor the status of the plant while proceeding to a cold shutdown condition not included in the Design Document.

The accumulator are pressure, accumulator isolation valve status, and accumulator nitrogen vent valve status were identified as Category 2 only if the plant has committed to safety grade cold shutdown.

9.

The Westinghouse Owner's Group Emergency Response Guidelines do not consider boric acid charging flow as a parameter to be used by operators during or following an accident.

Under these conditions borated water is pumped from the large volume RWST into the RCS.

BVPS-2 has designated RWST level, HHSI flow, LHSI flow, containment water level, and emergency core cooling system (ECCS) valve status for monitoring the performance of the ECCS since the ECCS does not normally take suction from the boric acid tank.

If boration is used following an accident, qualified charging flow indication and RCS sampling are used to demonstrate that the RCS is being adequately borated.

10. The installed instrumentation is designed to Category 3 criteria and the measured temperature is from O'

to 200*F.

The Westinghouse Owner's Group Emergency Response Guidelines do not require operator action based on containment temperature indication, but rather use containment pressure indication, therefore containment temperature is considered a Category 3 parameter, and the existing range is adequate for normal j

operation.

11. The Westinghouse Owner's Group Emergency Response Guidelines do not require operator action based on containment sump water temperature indication.

At saturated condition, sump water Amendment 5 10 of 11 February 1984

BVPS-2 FSAR NOTES TO TABLE 7.5-1 (Cont) temperature can be inferred from containment pressure.

containment spray system valve status and containment spray flow indications are used to demonstrate that the Emergency Core Cooling System is operating properly when taking suction from the containment sump.

12.

Note that although these valves are classified as Category 2, the associated instrumentation meets the qualification requirements for Category 1 instrumentation as discussed in FSAR Section 7.5.2.1.3.1, with the exception of 2CHS*FCV160 and 2CHS*HCV142 See. Table 6.2-60).

These valves are closed during normaI(plantoperation and post-accident conditions,: and are powered from non-Class 1E sources.

13.

Under Implementation Date,

" complete" means that this instrumentation already exists in the current design.

All instrumentation will be installed by fuel load unless otherwise noted.

I i

14.

The main steam pressure transmitters are environmentally qualified for all events with the exception of the arbitrary 1.0 fta MSLB in the main steam valve house imposed by NRC-BIP-ASB 3-1.

The resultant environment produced by the 1.0 fta break exceeds the qualified temperature of the transmitters' instrument cable.

Failure of the cable has no y

adverse effect on RPS or SLI signal generation as the cables perform these functions prior to exceeding their qualified temperature.

For the purposes of monitoring heat removal during plant cooldown following this specific event alternative class 1E-powered instrumentation is available in the form of steam generator level, auxiliary feedwater flow, and RCS temperature.

These variables provide sufficient l

indication that the steam generators have been isolated, that level is being maintained, and that primary system heat removal is in prograse r puscar IC en H4 7' S4dkr M WR = Wide range.

NR = Narrow range.

• = Range / Status information for radiation monitors is not final.

• • = Sufficient to monitor anticipated rates (refer to Section 12.5.2.2.3).

d.

4 i

15. The Hi Range Radiation Monitors are environmentally qualified for all l

events.

However, at maximum postulated containment temperatures, due to MSLB, accuracy within the lowest two decades (0-50 R/HR) of this monitor j,

may exceed a factor of 2 (Reg. Guide 1.97 criterion).

This is an acceptable condition since radiation levels within this range do not affect operator action and vefification of actual radiation levels can be obtained using a qual ified, backup radiation monitor located outside t

j containment near the personnel hatch.

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