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Revised Proposed Tech Specs Re Power Distribution Limits,Esf Instrumentation,Esf Actuation,Msivs & Radiation/Accident Monitoring Instrumentation
	ML19327B098
Person / Time
Site:	Millstone
Issue date:	10/16/1989
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML19327B097	List: ML19327B096; ML19327B098;
References
	NUDOCS 8910250194
	Download: ML19327B098 (12)
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< MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION l .

'3.7.1.5 Each main: steam line isolation valve (MSIV) shall be OPERABLE.

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APPLICABILITY: MODE 3 1, 2, 3, and 4.

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ACTION: i L

MODE l:

u .,.. With one- MSIV inoperable but open, POWER. OPERATION may continue ;

l provided the inoperable valve is restored- to OPERABLE status within 1

! 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise be in HOT STANDBY . within. .the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .and 'i L in HOT' SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . ;

l MODES 2, 3, and 4: )

.L With one' MSIV inoperable, subsequent operation in MODE 2 or 3 or 4 may L' proceed provided the isolation valve is maintained closed. Otherwise, be L in HOT. STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the ,

following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . !

SURVEILLANCE' REQUIREMENTS I

1 4.7.1.5.1 Each'MSIV shall be demonstrated OPERABLE by. verifying full closure

!. within 5 seconds in Modes 1, 2, and 3 when tested pursuant to Specification 4.0.5. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3. l

, . 4.7.1.5.2 Each MSIV shall be demonstrated OPERABLE by verifying full closure-L~

within 120 seconds in Mode 4 when tested purs.uant to Specification 4.0.5. The I provisions of Specification 4.0.4 are not appl.icable for entry into Mode 3. I s

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Millstone Unit 3. Cyets 3 Radial Pasking Factor Limit Reports for Four loop and Three Loop operation 6

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N WBSYINWOUSS PROPRIETARY C: ASS 3 Radial Peaking Faster Limit Report Four 1 mop Operation his Radial Peaking Faster Limit Report is provided in asserdance with Paragraph 6.9.1.6 of the Millstens Unit 3 puoloar Plant Toshnical specifiestions.

The four loop operation F limits for RATED THERNAL POUIR within 9

speettic core planse for Cyele 3 shall bei 1, . F"",7 less than or equal to 1.'/9 for all more planes containing Bank "D" oentrol rods, and

2. F" less than or equal to 1,67 for all unrodded more planes, Thess'F ,(s) limits were used to confirm that the heat fium het 4 ciaannel fastet F g (s) will be limited to the Toshnical Specification values of:

j F(s)$if][K(s))forP>0.5and, q

Fq (s) 5 l' 641 IK(s)) for Ps o,5 l

assuming that most limiting axial power distributions expected to '

result from the insertion and removal of Control Banks 8, C and D during operation, including the secompanying variations in the axial manon and power distributions as described in the " Power Distribution j

Control and Imad Fellowing Procedures". WCAP 8403, Septeabet,1974.

Therefore, these F , limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ICCS aseeptanas criteria of 10CFR50.46, see Figure 1 for a plot of [Fq T,P ] versus Axial Core Height.

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WESTINWOUSE FA0FE1ETARY CLASS 3 :

Radial Peaking faster Limit Report :

Three 14ep operation This Radial Peaking Faster Limit Report is provided in assordamse with' l Paragraph .6.9.1.6 of the Milletone Unit 3 Nuelear Plant Teeknisal :

spoeifications. .

The three loop operation F,7 limits for 656~of RATED THERMAL 70 m within specific sore planes for Cycle 3 shall be:

F 65 RTF less than er equal to 1.64 for all eers planes

1. i eentaining tank 'D' eentrol reds, and 65 RTP less than et equal to 1.53 for all unredded eers

2. F planes.

3. In the reistionship for F,,L the sultiplier M7,7 is equal to A

. 0.312.

I These Fg (s) limits were used to confirm that the heat flux het ehannel factor F q (s) will be limited to the Technical Specification

" values of Fg (s) $ (f) (K(s)) for 0.65 g F > 0.325 and, p

F9(s) $ 15.20] (K(s)) for P s 0.325 i l

assuming that most limiting axial power distributions expected to ;

result from the insertion and removal of control Banks 5, C and D during operation, including the aceospanying variations in the axial L ,

zonen and power distributions as described in the " Power Distribution I Control and Imad Fe11 ewing Procedures', WCJL* 8403, September,1974 l

limits provide assurance that the initial Therefore, these F,7 l eenditions assumed in the thCA analysis are met, sleng with the ECCS t acceptance eriteria of 10CFR50.46. l l

see Figure 2 for a plot of (F . Pg,g) versus Axial Core Height, l

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PggL VERSUS AXIAL CORE HEIGHT DURING WORMAL CORE 3 LOOP OPERATION r

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ATTAcilNEllT 1 Suggested Revision to Toshnical Specification 4.1.1.2.2.s and navised Three 14ep Radial Peaking Factor Limit Report 5

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, MbER DISTRIBUTION LIMIT 8 )

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.4.2.3.2.1 The previsions of Specification 4.0.4 are not applicable.

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l>, 4.t.8.2.8 F, shall be evaluated to determine if gF (Z) is within its limit by: l

e. Using'the' movable incere detectors to obtain a power distribution esp at any THERMAL POWER greater than 5 of RATED THEWL POWER, .

b. Increasing the measured F, component of the. power distribution map by 5 to account for manufacturing tolerances and further increasing the value by N to account for seasurement uncertainties, 0

c. Comparing the F temputed(F9)obtainedinSpecification 4.2.2.2.26 o

above to: Y

1) The F limits for G N of Raft 0 THERMAL POWER (F $ RTP) for the i

, 9 appropriate measured core planes given in Specification 4.2.2.2.te, l and f., below, and

2) The relationship L '

8 Fy=F'f887P(1*p ([P)),

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Where F,' is the limit for fractional THERMAL POWER operation 0 65'RTP expressed as a function of F ,My is the F , multiplier, andPisthefractionofRATEDTHERMALPkRatwhichF W was measured.

d. Remeasuring F, according to the following schedule:

1) When F isgreaterthantheFh65RTPlimit for the appropriate esasured core plane but less than the F relationship, additional l

c 0 power distribution maps shall be taken and F,y compared to F andr;either

's) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 205 of RATED THERMAL POWER er greater, the THERMAL POWER at was last F *C which deterwined, or b) At least once per 31 Effective Full Power Days (EFPD),

whichever occurs first.

3/4 2-12 007075 MILLSTONE - UNIT 3

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WRITINB10 DOE PRORIETARY CIASS 3 s . .

Radial Feeking Footer Limit. Report Three 14ep Operation I

This Radial' Peaking Faster Limit Report is provided in asserdance with Paragraph 6.9.1.6 of the Millstone Unit 3 Nualear'Flant Tsehnical r Spesifications.

The three loop operation F limits for 65% of RATED THERNAL P0irER ;

within specifie sore planss for cyste 3 shall bei-

1. F 65 RU loss than er equal to 1.81 for all eere planes sentaining Bank "D" control rods, and :

2. F 65 RU less than or equal to 1,69 for all unrodded oore !

- Planes. ;

3. In the relationship for F I' the multiplier is equal to 0.281. t L'

1 These Fm (s) limits were used to confirm that the heat flux hot channel factor Fg (s) will be limited to the Technical Specification l

values of:

Fq (s) 3 [ ] [K(s)) for 0.45 g P > 0.325 and, !

i Fq (s) 5 (S.20) (K(s)) for P $ 0,325 assuming that most limiting axial power distributions expected to i result from the insertion and removal of control Banks 5, C and D during operation, including the accompanying variations in the axial zonen and power distributions as described in the " Power Distribution Centrol and Lead Fellowing Frecedures", WCAP 8403, September, 1974 Therefore, these F limits provide assurance that the initial senditions assumed in the IDCA analysis are not, along with the Ecc5 aseeptance criteria of 10CFR50.46. .

See Figure 2 for a plot of [F .Phl) versus Axial Core Height.

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Millstone Nuclear Power Station,. Unit No.' 3

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l0ctober 16, 1989 Millstone Nuclear Power Station, Unit No. 3 Examples of F L using the xy ,

Current and Proposed Relationshios n

Current Proposed

.fhy-1.53[1'+.312(1- P)] Unrodded Fhy-1.69[1+.281(.65- P)] Unrodded L

.65 xy - 1.69 Fhy-1.69 P F 3, P = .5 Fhy-1.76 Fhy-1.76

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- 1,64.[1 + .312.(1 - P)] Rodded Fhy-1.81{1+.281(.65- P)] Rodded L

'P .65 F xy - 1.81 Fhy-1.81 o

L P = . 5. Fhy-1.89 F xy - 1.89

<1 Additional surveillance' required when Additional surveillance required when f,. Fhy is between 1.53/1.64 and the limit. Fhy is between 1.69/1.81 and the limit, y

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ML19327B098

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