ML20024G704

Proposed Tech Specs Re Field Breaker Recirculation Pump Trip Sys

ML20024G704
Person / Time
Site:	Monticello
Issue date:	03/01/1978
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G349	List: ML20024G348 ML20024G350 ML20024G704
References
NUDOCS 9104250416
Download: ML20024G704 (8)

Text

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, E. Reactor Building Ventilation Isolation an 1 49 .:

8$

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Stnndby Gac Trentment System Initiation ' '

. 1 1 04i F. Recirculation P' imp Trip Initiation 49 tpa) 1 f 00 $

3.2 lhses

'oc8o fu - 6h ~I, i' 2 0*

(J h.2 Ihses 71 g r. _ i 3 3 and h.3 Control R>d Systen 75 - '

i i

A. R"netivity Limitations 75

, B. Control iiod Withdrnun1 76 I 4

C. Sern= Insertion Times ,

i 79 D. Contml Rod Accumulators i

80 [

E. Benetivity Anomslies o

81 ~

l 3 3 and h.3 Ihses -

82 J

I l 3.4 and b.h Standby Liquid Contml System 68 [

A.  ;

?brm1 Operation -

88 i

B. Operation with Inoperable Components .

89 I C. Volume-Concentration Requir-ments 90 l

t l 3.h and 4.h Bates 94 i 3 5 and 4 5 Core and Containment Cooling Systems

'96 t '

A. Core Sprny System ~ i

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96 i B. LPCI Subsystem 98 7

i l C. TlIR Service 'Jater System 101 l

I ii REV t . .. . . - - _ _ _ _ _ _ _ _ _ - - _ _ _ _ - _ _ - _ _ - _ _ _ _ _ _ _ . . _ _ _ _

1,lST OF TA Hf 1:'i 3.1.1 Reactor Protect ion System (Scram) Instrument Re<ps i rement s 30 4.1.1 Scram Inst rument Tunctional Tests - Minimum l'unctional Test Irequencies for Sa fety Inst rument:st ion and Cont rol Ci rcui t s 34 4.1.2 Scram Instrtment Calibration - Minimsm Calibration I requencies for Reactor Protection Inst rument Channels 36 3.2.1 Instrtwentat ion that initiates Primary Containment I solat ion Fernct ions 50 3.2.2 instrumentation that Initiates Emergency Core Cooling Systems 53 3.2.3 Instrumentation that Initiates Rosi Block 57 3.2.4 Instrumentation that Initiates Reactor Bulleling Vent ilation Isolation and Standby Gas Treatment System Initiation 60 l 3.2.5 I ns t rumen ta t ion tha t Initiates a Recirculation Punp Trip 60A 3.2.6 Trip Functions and Deviations

! 69 4.2.1 Minimum Test and Calibration Frequency For Core Cooling, Rod Block and Isolation Instrumentation 61 3.6.1 Safety Related Ilydraulic Snubbers 121B 4.6.1 In-Service Inspection Requirements for Nnticello 124 3.7.1 Primary Containmerit Isolation 153 4.8.1 Sample Collection and Analysis - MPiticello Ptcler .enerating Plant - Radiation Envirorrental Monitoring Frogram 169 6.5 l Protection Factors for Respirators 206

ix REV

1 r

i 4 3.0 LIMITING CO'!DITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

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l E. Reactor Building Ventilation Isolation and St andby Gas Treatment System Initiation

1. a. Except as specified in 3.2.E.1.b below, four radiation monitors shall be operable at all times.

4 1

b. One of the two monitors in the venti-lation plenum and one of the two radia-  !

tion monitors on the refueling floor may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the

' inoperable monitors are not restored to service in this time, the reactor build-ing ventilation system shall be iso-lated and the standby gas treatment system operated until repairs are complete.  ;

2. The radiation monitors shall be set to trip as follows:

(a) ventilation plenum i 3 cm/hr (b) refueling floor 6100 mr/hr '

3. When irradiated fuel is in the reactor vessel and0 the reactor water temperature is above 212 F, the limiting conditions for operation for the instrumentation listed in Table 3.2.4 shall be met.

F. Reci rculation Pump Trip Inttiation

1. Ebenever the reactor is in the RlU Mode, the 2

limiting conditions for operation for the i n s t ricen ta t ion listed in Tr'le 3.2.5 sh.111 he not.

3.2./4.2 '

. 49

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i Table 4.2.1 - Continued

?tinimum Test and Calibration Frequency for Core Cooling.

Fod 511ock and Isolation Insttwntation I n st rument Channel Test (3) Calibration (3) SeS52r Check O)

. 3. Steam Line lov Pressare No t t. 1 Once/3 mnths Ibne i 4 Ste m Line I!igh Radiation Once/veek (5) Note 6 Once/ shift ljPCI ISOIATION

1. Steam Line fligh Flow Note 1 Once/3 mnths No e

2. Steam Line Hir.h Temperature Note 1 Onec/3 runths None RCIC IS01ATION 1.

Stea:n Line fligh riov Note 1 Once /3 months None l

2. Stea:n Line !!!gh Temperature Note 1 Once/3 months None f RFACTOR BUILDING VENTI 1ATION

! 1. Radiation Monitors (Pltnum) Once/3 months 2.

Note 1 Once/shif: i Radiation Monitorn (Refueling Floor) Note 1 Once/3 months (4)

O_FF-CAS ISOIATION

1. Radiation Monitors (Air Ejectors) Notes (1,5) Note 6 Once/ shift RT:CT RCU1ATION PCi? TRIP

1. Reactor Iligh Pressure Note 1 Once/ Operating Cycle- Once/ Day Transmitte r f'nce/3 Months- Trip Unit

2. Reactor lev Uater Level Note 1 Once/ Operating Cyc le - Once/ Day '

T ransmit te r  !

Once/3 Months- Trip Unit roTCS:

L (t) Initially once per month until cw m w rr (M a s defined ~igures 4.1.1) is 2.0 x 10 5, thereaf ter accordirg t i Figure 4.1.? vith an L t:

• nei not g o ette r ? D - no mn the .

3.2/4.~ 62 i

Bases Continued-L2 For effective emergency cote cooling for the small pipe breik the HPCI or Automtic Pressure Felief system must function since for these breaks, raactor pressure does not decrease rapidly enough to allow either iore spray or LPCI to operate in time. The arranr.*-ent of the t ripping r ntacts is such as to p r ovi t'e this function when necessary and minimize spurious operation. The trip settings given in tha specification a.e adequate to assure the above critaria is met. Feference Section 6.2.4 and

6. 2. 6 IMR. The specif ication preserves the ef fectiveness of the system during periods of main-tenance, t es t in g, or calibration and also minimites the rink of inadvertent operation: 1.e., only one instrument <henet out of service.

i Two air ejec tor of f gas monitorr. are provided and when their trip point is reached, cause an isola tion

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of t ha air ejector off-gas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip or two drunstale. There is a 30-minute delay before recoeiner

• rain Inlet valve closure when the recombiners are in use and a 15-minute delay before off gis isolation valve closure when the recorhiners are bypassed in which the reactor operator may take corrective action. Both instruvnts are required for trip. The trip settings of tha in atronent s are set so that the maximum stick releas* rate limit is not exceeded.

Four radiatit:n moniters are provided which init iate isolation of the reactor building and operation of the standby gas t r ea t tnen t system. The monitors are located in the reactor building ventilation plenum and on the refueling floor. Any one upscale trip will cause the desired action. Trip settings of 'l mR/hr for the monitors in the ventilation duct are based upon initiating normal ventilation iso-lation and St andby Gas Treatrw nt System operation so as not to exceed the maximum release rate limit for the reactor building vent. Trip settings of 100 mR/hr for the monitors on the refueling floor tre based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the reactor building via the normal ventilation stack but that all the activity is processed by the standby gas treatment system.

The recirculation pump trip description and performance analysis is discussed in Topical Report NEDO-25016, September 1976, " Evaluation of Anticipated Transients Without Scram for the Menticello Nuclea r Generatine, Plant". (See September 15, 1976 letter from Mr 1. O Mayer, NSP, to Mr D L Ziemann, USNRC.) The pump trip is provided to minini=e reactor pressure in the highly unlikely event of a plant transient coincident with the failure of all control rods to scram. The rapid flew reduction 1

3.2 r.ASU 68 REV

r Bases Contirned:

increases trip in the core eventvoiding, a negat.ive of an isolation reactivity feedback. Iligh pressure sensors initiate the pump transient. Iow level sensors initiate the trip on loss of feed-water (and the resulting MSIV closure). The recirculation pump trip is only required at high reactor power levels, where the safety / relief valves have insufficient capacity to relieve the stenta which continues to be generated after reactor isolation in this unlikely postulated event, requiring the trip to be operable only when in the PN mode is therefore conservative.

• Although the operator will sat the set points within tha 3.2.3. 3.2.4, and 3.2.5, the .sctual values of the various settrJppoints settings car.specified in Tables 3. 2.1. 3.2. 2, value the operator is attempting to set. The dif fer appreciably f rors the cperator setting error, drift of the set point,deviatiens could be etc. Therefore, caused by inherent instrument error, for in the variotis transient analyses and the actual trip **ttings easy vary by the follthese deviations have been a owing amounts.

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3.2 MSES 68A REV I

l Ta bi c 1.2.6 Trip Functions im4 D>vintions Trip i^ unction Deviation Reactor Ibilding Ventilation Isolation and Ventilstion Plenun 40.2 Mr/Hr '

Standby Gao Trentrent System Initiation P.ndintion Monitorn Opecification 3 2 E.3 and Tnbla 3. P.1+

Perueling Floor PMlation Monitern +5 Mr/Hr l Icv Icactor Water Icvel 6 inches High Pryvell FWanure + 1 poi Prinnry Contairnent Inointion Functions Icv inv Water IcVel -3 inches Table 3 2.1 Iligh Flov in Mnin Steam Line +2 %

Hir,h Temp. in Mnin Steam +2 F Line Tunnel Icv Pressure in Main Steam -10 psi Line Ilir.h IYyvell Pressure +1 poi Irv Feneter Wei,er '-vel -6 inches IG'CI Hirh Steam Flow +7,500 lb/hr IU'CI Steam Line Area High +2 F M.

PCIC High Steam Flev +2250 lb/hr PCIC Steam Line Aren High M +2 F 69 32 VFES ggy i

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! l l Tabic 3.2.6 - Centinued Trip Function and Deviations l

j Trip Function Deviation i Instrumentation That Initiates I:nergency Lew-Lev Reactor Water Level -3 Inches i

Core Cooling Systems Table 3.2.2 Reacter Low Pressure (Pump -10 psi i

" tart) Pe rmissive  !

r l High Drywell Prensure +1 psi  !

Low Reactor Pressure (Valve -10 psi ,

! Pe rnissive t l

Instrumentation that initiates IRM Dewnscale -2/125 of Scale I Red Bloc 1t IRM Upscale +2/125 of scale j Tab le 3.2. 3 i 1

APRM Downscale -2/125 ef Scale

APR:1 Unscale See Basis 2.3 - Page 24 ,

I RBM Downscale -2/125 of Scale [

R3M Upscale Same as APRii Upscale i 4

I Instrumentation That Initiates High Reactor Pressure + 12 psi I Recirculation Pump Trip Low Reactor Etter Level - 3 Inches A violation of this specification is assumed to occur only when a device is knewingly set outside of the 10miting trip settings, or, when a sufficient. number of devices have been affected by any means such that the automatic function is incapable of operating within the allowable deviation while in a reactor mode in which the specified function must be operable or when actions specified are not initiated as specified. ,

6 b l i 40 REV 3,2 P>tS ES

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