ML20213E550

Lists Tech Specs Reviewed by Branch,Per 830701 Request. Radiation & Fire Protection Instrumentation Not within Branch Scope.Tech Specs Acceptable,Subj to Listed Exceptions

ML20213E550
Person / Time
Site:	Columbia
Issue date:	08/11/1983
From:	Rosa F Office of Nuclear Reactor Regulation
To:	Thomas C Office of Nuclear Reactor Regulation
References
CON-WNP-0633, CON-WNP-633 NUDOCS 8308180653
Download: ML20213E550 (4)

Text

r

}cekel

/s 6 gg j

• m o't my' y t>E!!0RAUDU:1 FOR: C. Thomas, Chief, Standardization a Special Projects Branch Division of Licensing FR0;1: Faust Rosa, Chief Instrumentation 4 Control Systens Branch Division of Systems Integration

SUBJECT:

UtlP-2, ICSB REVIEU OF TEClitlICAL SPECIFICATI0i:S Plant Name: WriP-2 Docket flo.: 50-397 Licensing Status: CL 33 IG E ED c2Iorz g Responsible Branch: LB #2 Certiffed 3y Project Manager: R. Auluck *, 7 w. s Review Branch: ICSS  %

Review Status: Incomplete for this iten.

As requested by memorandua dated July 1,1983 (C. Thomas to Branch Cniefs) tne Instrumentation and Control Systens Branch (ICSB) has reviewed the UitP-2 Technical Specifications within ICSB's scope. ' A list of the Tech-nical Specifications reviewed is attached. Please note that radiation and fire protection instrumentation are not within the ICS8 scope. With tne exception of the items listed below, ICSB has detemined tnat the WMP-2 Technical Specifications are acceptable.

The following Technical Specification iteas have been ciscussed witn von ifoff; nan of your staf f:

1. ICSB has identified deficiencies in tne metnod used to establish protection system trip setpoints anu allowaole values contained in the tecnnical specifications. In addition, the applicant has not deaonstrated Inat the methodology used to combine and account for instrument channel errors (in establishing the trip satpoints and allowable values) is acceptable. These concerns were identified in a memorandum dated August 2, 1983 from R.U. Itouston, DSI to T. flovak , DL. A request for addi-tional infomation and a proposed license condition were enclosed to this memorandu:a. Le will continue our review of tnis iteil upon receipt of the requested in-formation. Technical Specification cnanges are expected to ce requirec as a result of tnis review.

2. ICSB has identified potential deficiencies regarding tne capability for testing protection systeoi actuation logic at uhP-2. Specifically, the DUP-2 desisn does not appear to allow for at power testing of the final actuation logic 930818065 830811 W

F- ,c, w:

}

g

-k. neisuur,,

ADOCK 05000 ,397 m

( l7 ~ l i F-

• = "

• X29451  !  ;

ww T T

, .+.

sc som ns no-sa r.acu om CFFICIAL RECORD COPY

. L Tho. ra s .

(e.g. , the A:;U function of the one-out-of-two taken twice logic: A or C Ai!D 8 or J) without initiating the protective function. Consequently, this logic is only i:eing tested at refueling outages (i.e., roughly once per 18 rontns). This concern appears to be applicable to .:.ost of the engineered safety features (ESF) systeas sucn as the tr:ergency core cooling syste.as (HPCS, ADS, LPCI), RCIC, and reactor vessal dnd Contdintlent isolation syste:Js. The reactor trip system logic is fully tescanle at power and is not subject to this concern.

The staff has previously discussed this concern uits the' applicant during the ICSd sita visit on April zo and 27, 1983. Additional neetings to discuss this concern (and tne concerns listed in iten 1 above) are currently sched-uled for late August 1983. At this time we do not l odlieve it is appropriate to condition tne W!P-2 license pending resolution of this concern. Design modifications to allow at power testing of the actuation logic ,aay be eventually required, t'e therefore reco. rend issuance of the utiP-2 Technical Specifications with tha present 18 aonth (rerueling outage) actuation logic surveillance frequencies for tne interia. However, it should ne noted that Technical Specification changes are expected to be required for at power testability of the final actuation logic at frequencies com:nensurate wf tn che i.aportance of the protective functions performed by these systens. We will keep you informed of the status of t;11s itan.

3. In a me..;orandua (R. I'.attson to d. Eisennut) oated Deca:aber 30, 1942, the ICSB proposed technical specification caanges to audress the operability of remote shutdown systers re-quired under the provisions of GLC 19. These caanges im-pose limiting conditions for operation and surveil. lance requirements on transfer switches and control circuits for the re.10te shutdown systen and impose operaoility require-

"'C" k ... .. ..... . . . .. ...... ............. . ... .. . . .. . . .. .. . ..

(anavep........... I  :

A" ,... .. .......... ...... ............h... i

, ..... 3 nc cav m oo_aci sacu om OFFICIAL RECORD COPY

2 C. Inomas .

aents on both channels of nonitoring instru".cnts. It was q recounended in the Deceaber 30, 1932 meraorandtm tnist thesa changes be implemented inr.ediately on OL revieas. Therefore, .

Section 3.3.7.4 of tne WiiP-2 Technical Specificaticos shoulu '

oc modified to include these requirements.

eOriginal Si;;ned E'/ :

Fauct Ec 5a" Faust Rosa, Chief Instru :entation & Control Systeas Branch Division of Systens Integration Attachraant:

As stated DISTRIBUTION:

Docket File cc: x. Nattson ICSB R/F R.U. ifouston R. Kendall (PF)(2)

R. Auluck C. Rossi D. ioffman F. Rosa D. Brinkaan WNP-2 S/F R. Capro M. Virgilio ,

J. T. Beard J. Mauck D. Thatcher fi. Chiranal 4 .

l l

,6 t

P en:en ICSB/DSI T ' I J/.DS ICSB/DSI' l .

=~a-o Men.da11 ;c.t,,, CN' $, ,'FRoh... , ,, ,, , , . .,

.8./. . .i. ..

/. 8. 3. .. . 8. ./. /. .C. . . /. 8.. . 3.

8. /.. .. .,. . . . . . /. 8 3 . .  :

o'Yl . . .. .... . .. .. ,. . .. .. . . . . .. .. . . . . . .

.nc ron= v. . io..o . ~ncu ca" OFFICIAL RECORO COPY

t WNP-2 TECHNICAL SPECIFICATIONS <

REviEWE0 BY ICSB 2.2.1 Taole 2.2.1-1 Reactor Frotection System Instrumentation 3.1.3.7 Control Rod Position Indication System 3/4.3.1 Reactor Protection System Instrumentation 3/4.3.2 Isolation Actuation Instrumentation 3/4.3.3 Emergency Core Cooling System Actuation Instrumentation 3/4.3.4 Recirculation Pump Trip Actuation Instrumentation 3/4.3.5 Reactor Core Isolation Cooling System Actuation Instrumentation -

3.3.7.4 Remote Shutdown Monitoring Instrumentation 3.3.7.5 Accident Monitoring Instrumentation 3/4.3.9 Feedwater System / Main Turbine Trip System Actuation Instrumentation B 3/4.3.1.2.3.4.5, Bases for the above B 3/4.3.7.4,5 technical specifications B 3/4.3.9 DESIOIATED 02IGII!1L CertifiedSy[. ,.

,_o rw\,

. e- -

i

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