ML20085A304

Forwards marked-up FSAR Pages for Incorporation Into Amend to Show Conformance W/Srp (NUREG-0800)

ML20085A304
Person / Time
Site:	Satsop
Issue date:	06/16/1983
From:	Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0800, RTR-NUREG-800 GO3-83-481, NUDOCS 8307050270
Download: ML20085A304 (11)

Text

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Washington Public Power Supply System Box 1223 Elma, Washington 98541 (206)482-4428 Docket 50-508 JJne 16,1983 G03-83-481 Director of Nuclear Reactor Regulation ATTN: Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensina US Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NUCLEAR PROJECT 3 SUPPLEMENTAL INFORMATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAN (April-May1983)

Reference:

a) Letter #G03-82-1015, G. D. Bouchey to J. D. Kerrigan, dated October 6,1982.

b) Letter #G03-83-08, G. D. Bouchey to G. W. Knighton, dated January 4, 1983.

Reference a) transmitted amendment P to the WNP-3 FSAR. This amendment contained the initial phase of the wNP-3 Review for conformance with the Standard Review Plan (SRP) NUREG-0800, required by 10CFR50.34(g).

In those cases where differences between the WNP-3 design criteria and the SRP acceptance criteria were identified in the initial Supply System review, a schedule was provided detailing when the bases would be presented for con-cluding that the WNP-3 design criteria are in compliance with the Commission Regulations.

Presented herewith is the material for which comitments were made for the months of April and May.

Included are marked up FSAR pages to show the changes which will be incorporated into a subsequent amendment.

In those cases where exception is taken to the SRP acceptance criteria a reference is provided to the FSAR section where further information is provided.

If necessary, additional information will be added to the appropriate FSAR sec-tion indicated on the marked up FSAR pages.

In certain instances, following a detailed review, we have been able to con-clude based on information presented in the FSAR that the WNP-3 design cri-teria do, in fact, conform to the SRP acceptance criteria.

For these cases, with the exception of a change to the FSAR conformance review table (Table 1.8-3), no further change will be necessary.

8307050270 830616 g

PDR ADOCK 05000 g

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Mr. G. W. Knighton Page 2 June 16, 1983 SUPPLEMENTAL INFORMATION ON CONFORMANCE OF WNP-3 TO STANDARD REVIEW PLAN (April-May1983)

Reference b) provided the Supply System's commitment to follow the guidance of Regulatory Guide 1.97, Rev. 2, with exceptions. The WNP-3 position on this Regulatory Guide as it pertains to detection of containment sump leak-age must be changed as shown to accurately reflect our design.

If you require further information of clarification, the Supply System point of contact for this matter is Mr. K. W. Co'k, Licensing Project Manager (206/482-4428 ext. 5436).

Sincerely, G. D. Bouchey, Ma ager Nuclear Safety and Regulatory Programs AJM/ss cc:

D. J. Chin - Ebasco NY0 N. S. Reyonds - D&L J. A. Adams - NESCO D. Smithpeter - BPA A. A. Tuzes - CE A. Vietti - NRC Ebasco - Elma WNP-3 Files - Richland 1

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9 WNP-3 FSAR TABLE 1.8 3 NURrG - 0800 NRC STANDARD REviEU rLAN 000tL'.ANCE SRP/ACCErTANCE CRITf3fA TES 90 N/A RINARKS 11.5 Procese And Efflueet Radiolosteal Moottoring innermentation And Sampling systems Rev. 3 - July 1981 ACCEPTAllCT CetTEt!A E1$8 acceptance criterle for the process and effluent radfological sonitoring instrumentation and samp1tng systegs are based on meetin0 the releeant require-monts of the following regulations:

A.

10 CFR Part 20. $20.106 as it relates to redloactivity monftering of x

effluents to unrestricted areas.

General Design Criterten 60 as it reistes to the radioactive weste manage-g 8.

ment systees being designed to control release of redteactive materials h

W h d tJ, 6@

W-I to the environment.

General Design Criterla 63 and 64 as the/ relate to the radios:tive weste I

/

C.

management systees being designed to monitor radiation levels and leasege.

8 ##f bN

• )7 N

/

5pecific criterte necessary to meet the relevant requirements of the Commission

/

(

ih4N*rGS M fi k f

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m(I% 81. *>.1. 4.1 (.o i g.3. ( 7,a L3 regulations identified above are:

Provistens should be made fer the Instrumented monttoring or for the samp1tne x

3.

'g' and anaiyse, of.a n nor i and potentIai e.ffiuent p.th eys for reiesse of radio.ctiv..atrtestoth.environmentt.eet Gener.i oesign Crit.rton 6e To meet Critecton 64, the design of systees should sett the provisions of x See R'"' Y IU " '-

W a.

- -- "--- u *==

r Regulatory Guide 1.21 (Position C and Appendfx A) (Ref. 2)Ie)egulatory(Ref. 3).

'_.,,,a-R A.,;.

'a-

-s.,.

y and Regu'tatory Guide 4.15 (Position C) (Ref. 4)as appitcab Guide 1.97 (Position C and Table 1 ee Table 2

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1- -

2-The gaseous and Ifquid process streams or ef' fluent release points x

^

a.

should be monitored and sampled according to Tables 1 and 2.

x

_m.

For both OWRs and PWts. Itquid westes and confined volumes of gaseous y,,,g ; u L ;,,;;, _

y; y,,,,,

b.

waste should be soupled batchulse prior to rolesse, in accordance

. m,,, m.

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m,__

Continuous gaseous effluent monitors with Regulatory Guide 1.21.

e-e not required for open structs.res, such as Pwe turbine butidings

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4 or atmospheric vents f'er livid weste tanks containing treated er "c--

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2^^^

For Itquid processed Itquid waste and located outside of butidings.

end gaseous effluents that cannot be practicably monitored or sempted

(.

• batchwise, one of the following methods of representative saspilng should be provided:

(

{

?W A continuous proportioning sampilng system with at least two x See senerk Radielestest senttertns and e**Pltas (1) semple collection tanks. The systes should be designed to pro-of Isense and see,o. errg, g. g, i

t/8 vide a ftsed or measured finw retto of the sample collected to Provided batchetee, 4

L*

O the sampled stream discharge, or, alternettvely e w%:

i j

R (2) A periodic automatic greb sampling system with at least two I see me ark c%

semple collection tanks. The systee shoulit be desfgned to w

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ver-3 FSAR TABLE 1.8 3 s

IrUREC - o80n WRC STANDARD trVIEW FLAs sRP/AuiriAlett et1TERIA yr yo pyyg,gg 11.5 Procesa And Effleest Radielegical Monitoring Inst 1nmentattoe and sampitag Systema (coet'd)

Rev. 3 - July 1981 collect a fixed volume of sample at a rate proportfonal to the measured flow in the sampled stream discharge.

(3) Radioactive materials other than noble gases in gaseous effluents.

I See teenrk (1)

(1) Radtalosteel monitortns and sa=Pitna of iteute A continuous sampling system with replaceable particulate filter

,,4 aseeous af fluente ta providad batst.utas.

and radiolodine adsorber. The system should be designed to automat.

teolly take samples at e flaed or seasured flow rette of the semple throughput to the sampled strese discharge flew.

(M[.3 g;k %,

gfk 3hk For interef ttently operating effluent release palats, the systne should I

g l

be designed to automatically take samples whenever there is flow in a) C%L. l.0 w.'

cwhb a t ue the offiuent stre..

ex F5M bb..4 il.i. 2./4. If e) f.

For all of the above samples, a periodic analysis frequency for the g

collected samples should be specif f ed in the technical speciffcations.

su Lik oS it. s.q. t.z, f,i "S ~ '

2.

P*owlstons should be made for the instrumented monitoring of, or the g "' -

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perledfc or continuous samp1tng and analysis of, radfoactive waste T_'!!: "" _"^ ^ ^~^ * * **'T r i e r-t r "

^ " M 'r process systees. To meet Celteria 60 and 61, as they relate to radfe-M15tENWe-eemps6m++sth N"' ~d' a

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active waste systees and detection of excessive radf atten levels and Initiation of appropriate safety actions, the design of systres should

-eesotettone1rttthesewidad ay Deramhar_&es2.

4O meet the guidelines of Appendia 11.5-A (this SRP section), Regulatory Guide 1.21 (Position C as applicable), segulatory Guide 1.97 (Post-tionCandTable1orIable2.asappitcable),andRegulatoryGuide 4.15 (Position C).

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. wisfens should be made to assure representative sampling free g

a.

radfonctive process streams and tank contents. Recirculation pumps for liquid weste tariks (collection or sample test tanks) should be capabis of rectrculating at a rate of not less than twotankvolumeslnelohthours. for gaseous Ifou d process

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strees samples, prowlsions should be made for purg ng sample Itnes and for reducina plateout in sample lines. revisions forgaseoussamplingfromductsandstacksshouldbeinagreesent with AM51 N13.1. (Ref. 5)

Idhere practicable, provisions should be made to collect samples x

O b.

from process waste streams at central sample stations to reduce

^

1 leakage, spillage and radiatlon exposures to aperating personnel

.yW inaccordancewitliSRPSection9.3.z.

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Provisions should b made to purge and drain sample streams back x

t c.

to the systee of origin or to an appropriate weste treatment 0 J%

system.

Provisions should be onde for adelnistrative and procedural control

' O for necessary auxillary or ancillary equipment, and for special fealures 3.

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IntP-3 rsAR TABLE I.s-3 m1stC - Qo00 nRc sTseuo asview rus COMrLTAIICE Sar/ AcetrTANCE c1tTERI A Tr$ po N/A RIMARFS 11.5 Process Ana Effluent testolosteel Monstering Teatrureatetton Ana sampitag systems (Cont's) new, 3. July 1981

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s a-. so..

for the Instr oented radfological monitoring saapifns, and analysis x e - - "

'n 0;

-;'m fomeetCrIterion63andCrlterfon

_,,u.,u..a,u -,,--.

,_szu s.-weneme+-to-.

of process and effluent stre ms.

s.s _. :-, a w - _ __1;;, a.; m m w as they reiste to radioactive weste process systees and effluent

'- -- --tens.

. i. r-u.aca yt ch ab.w ees.*%

64 ths, the design of systees and the laplementation ef adminfs-discharge trative procedural controls she,uld meet the guldelines of Appendt s w sag u,

sa. thy m s_19a2.,

11.5-A(thsSRPsection) te l Gide1.21(PositionC)andRegula-

. fey Gv!da 4.15 (Position,C).gu atory u Instroentation samp1fng, and monitoring prowlstons should cor. fore to the following,:

Samp1 fag frequencies, required analvses, instroent alare/trfp K

---s m __ ;., :ty-1 a.

setpoints calibration and sensitivities and prowlsions for preparing,compositesamplesforlow-levelanalysesshouldbein conformance with pegulatory Guides 1.2: and4.15. Samp1fng frequencies and required analyses shou' d be elven in tne plant technical specifications; these provis' ons will be revfeued at r'

the OL stage.

fI Inst station and g

I b.

PE1!tSshouldbemadeforthenecesskgrossYphaseasurements, 3

to perfore gross beta-aames a fisotopic analyses and other routine analyses in conformance with Regulatory Gu,ide 1.21 Prowlslens should t,a made to perfore routine instrument calibra-

._xas n-,k n) _

c.

tion, meintenance and inspections in conformance with guidelines ofRegulatoryGul8e4.15. The frequencies of such actions should be elven in the plait technical specifications. The provisions will be reviewed et the OL stase. Provisions should also be made to replace or decontaminate monitors without opentne the process systee or losing the capability to isolate the effluent strees.

or diversion valves wfth automatic r

d.

Isolation valves, dampers,ll In the closed or safe posjtlon.

control features should fa IV 5etpo'ints for actuation of automatic control features Mitiating actuation of Isolation valves, dampers, or di rsion vaives should tjens. Non-ESF

,a o be estab11shed la the olant technical speciff instrumentation provislons for automatic tere nation or diversten E :p of releases should.onfore to the design guidance coritained in n

Appendia 11.5-A (this SRP section). E5F instrumentation prowlstens for gt automatic tereination or diversion of releases are reviewed in O

$ J3 5AP Section F.6 by IC58.

Prowlstons should be ande for the instr oented moniterf or samp11ag

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and analysis of identified gaseous offluent paths in the event of postulated accfdent releases. To meet Criterien 64, as It relates

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- 163 2W-5 a

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This monitor is located on the 362.5 f t. level of the Reactor Auxiliary l

Building.

It takes a sample of the water discharged from the gas stripper and returns it to the sr.e line. Physically it is a fluid stream monitor as described in Subsection 11.5.2.3.2, and it requires a 1

sample pump. In this case the microprocessor has been removed from the

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skid and placed on a nearby wall to protect it from possibly higt radiation fields present near the skid.

The measured activity levels are automatically transmitted to the system computer where they. are recorded and available for display j

through the system CRTs. If the activity exceeds pre-established setpoints-an annunciation is made through the system CRTs and event typer.- The receipt of these alarms will alert the operator so that additional radiation surveys, sampling and analysis can be effected in order to determine the cause of the problem. The alarm setpoints are to b : set between the measured activity levels of the degasified reactor. coolant and the maximum level of contamination permissible in this system. The setpoints may be adjusted continuously over the entire range of the monitor. The range of the monitor is from 10-4 to 10 pCi/cc which is the practical range of interest for normal power operation using a simple single detector radiation monitor.

e)

CVCS Le tdown Radiation Monitor The CVCS letdown radiation monitor will alert operations personnel to

! an increase in the radioactive contamination of reactor coolant as a[

quickly as possible, g m=

This monitor is located on the 373.5 f t. level of the Reactor Auxiliary Building.

It receives a continuous sample of the CVCS letdown, in

. parallel with the boronometer and is upstream of the purification filter. System process travel time delays the sample for approximately 2

two minutes delay to allow activation products with short half-lives, particularly N-16 to decay.

Physically, it is a fluid ar eam monitor

{

as described in Subsection 11.5.2.3.2, which does not require a sample pump.

In addition, two modifications havg been made, first the microprocessor has.been removed from the skid and placed on a nearby

. wall to pro,tect it from possibly high radiation fields present near the skid, and second a removable attenuator has been provided which may be manually placed between the sample volume and the detector.

The measured a'ctivity levels are automatically transmitted to the system computer where' they are recorded and available for diglay through the system CRTs.. If the activity exceeds pre-established setpoints, an annunciation is made through the system CRTs and event I

typer. The receipt of these alarms will alert the operator so that j

additional radiation surveys, sampling, and analysis can be performed l2 I

in order to detemine whether the increase of contamination is due to damage to the fuel cladding or due to some other cause such as 'a crud burst or iodine spiking. The level of the setpoints 'will have to be adjusted periodically during operation to allow for the gradual buildup of contamination in the reactor coolant. The cetpoints may be adjusted

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continuously over the entire range of the monitor. The range of this i=r S ct) 5'5C D 11.5 Amendment No. 2, -(12/82) :

Insert 1

.This monitor will be used in lieu of the High Range Circulating Primary i

Coolant Monitor required by Regulatory Guide 1.97 Rev. 2 for the detection of. fuel cladding failure. Regulatory Guide 1.97 recommends that Category 1 redundant detection systems be installed to measure this parameter. The recommended range is from 1/2 the Technical Specification limit up to 100 times the Technical Specification limit in Rads per hour.

There is no in-

' strument available to accomplish this, additionally instrumentation in this range would be saturated by N16 Thus its capability would be unavailable until after shutdown.

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1 1647W-7 WNP-3 FSAR There are four of these monitors. The sample points f or two of them are located on the 362.5 f t. level of the Reactor Auxiliary Building. One of these samples air being exhausted f rom the north side and the other samples air being exhausted f rom the south side of the 335 f t. le vel. The other two sample points are located on the 390 f t. level of the Reactor Auxiliary Building. One of these samples air being exhausted f rom the north side and the other f rom the south side of the 335 f t. and 362.5 f t. le vels.

The air samples are withdrawn f rom the exhaust ducts through a multipoint isokinetic sampling nozzle array (per ANSI 13.1) f rom a point downstream of the confluence of the ducts carrying exhaust air f rom the area being monitored.

In each case the sample is routed to a skid mounted radiation monitor that is located within a few f eet of the sample point. The sample pump is mounted on the monitor skid. Physically this monitor is a two stage airborne monitor as described in Subsection 11.5.2.3.3.2 which uses a moving particulate filter.

The measured activity levels f or both the particulate and gas channels are automatically transmitted to the system computer where they are recorded and amilable for display through the system's CRTs as described in Subsection 11.5.2.

If the activity exceeds pre established setpoints an annunciation is made through the system's CRTs and event logger.

The receipt of these alarms will alert the operator to the presence of an unusual level of airborne radioactivity coming f rom a paricular area so that additional surveys, sampling and equipment isolation can be effected in order to locate and control the source of the contamination. The setpoints may be adjusted over the entire range of the monitor. Additional infermation about

_ypfQ this monitor may be found in Table 12.3.4-2.

r-12.3.4.2.3.1.2 Control Room Air Intake Radiation Monitor The Control Room air intake radiation monitors provide plant operations personnel with measurements and records of the radioactive contamination of l

air entering the Control Room ventilation system. If the measured contamination exceeds pre established limits these monitors produce a signal to automatically isolate the Control Room air intake and thereby protect the I

habitability of the Control Room.

l These monitors are located in both the Control Room air intake plenums which are on the 442 f t. level of the Reactor Auxiliary Building. Refer to Figure j

12. 3-5a. There are a total of fcur monitors, two in each of the two plenums.

The detector assembly f or each monitor is mounted f rom the plenum ceiling and 7

observes air downstream of the tornado missile protection but upstream of the intakes isolation valves louvers. This location permits the continued observation of the contamination of the outside air af ter the intake has been isolated.

Each Control Room air intake radiation monitor is similar to a refueling pool area radiation monitor (Subsection 11.5.2.4.11) except for its detector i

assembly and some changes in its microprocessors sof tware. A schematic diagram of one of these monitors is shown on Figure 12.3-32.

These monitors are seismically qualified, Class IE and powered in pairs f rom the A or B saf ety busses using the same bus as their respective air intake.

Sc N MTR. l 12.3-32 Amendment No. 1, (10/82)

~

Insert 2 These monitors which can detect airborne radioactive material leaking from Containment will be used in lieu of the intermediate range Area Radiation Monitors recommended by Regulatory Guide 1.97 Rev. 2 for detection of a Con-tainment Breach in areas with penetrations and hatches (Type C Variable).

An increase in radiation levels in these areas would be due primarily to streaming through the per.atration or direct shine from the containment caused by~ elevated exposure rates inside containment.

Thus, any additional

^

increase due to airborne radioactivity leaking from the containment would not be discriminated by the area radiation monitors suggested by Regulatory Guide 1.97 Rev. 2 from streaming or direct shine.

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wwa-3 FSAR TAELE 1.0-3 WUREC - 0800 WRC STANDARD REVTEW FLAN COW LIANCE TES NO N/A REMARKS SRF/ ACCEPTANCE CRITERIA 10.3 Main Steam Supply System Rev. 2 - July 1981 ACCEPTANCE re1TERIA Acceptability of the design of the M555, as described in the app 1tcent's safety analysis report (SAR), is based on specific general desfgn criterla arHI regulatory guides.

The design of the M555 ls acceptable if the integrated design of the system is in accordance with the following criteria:

1.

Genersi Desfon Celterton 2, as related to safety-related portions of the x

systes being capable of withstanding the ef fects of natural phencoena such as earthquakes, tornadoss, hurricanes, and floods, and the positions of 1

the following:

Regulatory Guide 1.29, as related to the selsele design classification x

e.

of system components, Positions C.1.a. C.1.e, C.1.f. C.2, and C.3.

rf b.

BeCulatory Guide 1.117, as related to the protection of structures, x

systees, and components important to safety free the effects of tornado ofssiles Appendia Positions 2 and 4.

General Desfgn Criterton 4, wf** respect to safety-related portions of x

2.

the system being capable of withstanding the effects of external afssfies and inteenally generated etssiles, pfpe whtp, and jet 1spingement forces associated with pipe breaks, and the position of Regulatory Guide 1.115 as related to the protection of structures, systees, and components lepor-

. tant to safety from the effects of turbine alssfies, Position C.I.

3.

General Design Crfterton 5, es related to the capablifty of shared systees X see remark (1)

(t) There are no ehared erstem and and components fsportant to safety te perfore required safety functions.

coaronente et wr3.

General Oesf0n Criterton 34, as related to the systee function of transfer-I 4.

ring residuel and sensible heat free the reactor system in indfrect cycle plants, and the following:

(,A The positions in Branch Technteel Position R58 5-1 as related to the x

m e.

design requirements for residual heat removal.

,,yy Issue Nus$er 1 of NUREG-01?8 as related to cre'dtt being taken for

,b N#

(2) - _ P t. m.,_.

g_

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m..,

"--.aee in-all valves downstrees of the main steam isolation valves (MSIV) to

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p

.:= a-O Ifelt blowdown of a second steam generator b the event of a steen

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O W 3.^.li.,Ei"""~'c l"3l7 ~";";g-""p ifne br..a upstr.ae of the M5:v.

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No c, reach y k W,ig vot*Cs 6 h rvu h

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WNP-3 FSAR TAREE 3.8 3 emRtc - cano NLP M ANDARD BrVIEW PLAN COMrLTANCE sRP/ACCFrTANCE CRITERIA YES NO N/A RrH AR h3 9.5.1 Fire Protection Program Rev. 3 - July 1981 /

ACC[PTAIICE CRITIRIA The appilcant's fire protection program is acceptable if it is in accordance with the following criteria:

1.

10 CFR Part 50 550.48, and Generil Oesfon Criterton 3, as related to fire x see senerk (i)

, (t) The desssa of uNr-i s. correnti, i,,ing e,,in.2,a prevention, the design and operation of fire detection and protection against the req =trem. ate of torreo.48 and BTP systees, and administrative controls provided to protect safety-related CHFB9.$-I as part of the Saf e Shostdman Analvet s structures, systems, and components of the reactor factif ty.

.J appe ds, g,, io.ggo,,.

The Fire na4ard. Anat,.g.

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2.

General Desfon Criterfon 5, as related to fire protection for shared x see Resiark (2)

(2) qu.-

safety-related structures, systems, and components to assure the ability or c

,..n,nt..t war 1.

to perfore their intended safety function.

. The following specific criterla provide information, recommendations, and guidance and in general describe a basis ac:eptab'e to the staff that may be used to meet the requirements of $50.48, CDC J ana 5:

a.

Branch Technical Position (BTP) DIES 9.5-1 as it relates to the N see semark (1) design prowlslons given to laptement the fire protection program.

b.

Regulatory Guide 1.7g as it relates to libitable areas such as the x

control room and to the use of specific fire eatinguishing agents.

c.

Regulatory Calde 1.101, as it relates to fire protection emergency z

planning.

I 9.S.2 Cos ntcation Systeme Bew. 2 - July 1981 s.

I E

ACCEPTANCE CRlifRio Acceptability of the design of the cessuunlCatton system, as described {n the y

applicant's safety analysis report (SAR), is based in pa.-t on the degree of wY U

." N f*

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.