ML20077C503

Proposed Tech Specs,Revising Aprm,Rbm & RCS Setpoints & Allowable Values

ML20077C503
Person / Time
Site:	Hope Creek
Issue date:	11/28/1994
From:	Public Service Enterprise Group
To:
Shared Package
ML20077C502	List: ML20077C498 ML20077C503 ML20077C507 ML20077C513
References
NUDOCS 9412050151
Download: ML20077C503 (6)

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MARKED-UP TECHNICAL SPECIFICATION PAGES The following Technical Specifications for Facility Operating License NPF-57 are affected by this License Amendment Request: l 1

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Technical Specification Pace i'

Table 2.2.1-1 2-4 l

3/4.2.2 3/4 2-2 Table 3.3.6-2 3/4 3-59 6.9.1.9 6-20 l

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l 9412050151 941128 l PDR ADOCK 05000254 '

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IABLE 2.2.1-1 REAC 4 PROTECTION JYSTEM INSTRUMENTATION..SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT M(MfABLE VALUES t'l n 1. Intermediate Range Monitor, Neutron Flux-High 5 120/125 divisione s 122/125 divisione

@ of full scale of full scale 5 2. Average Power Range Monitort

a. Neutron Flux-Upscale, Setdown 5 15% of RATED THERMAL POWER $ 20% of RATED THERMAL POWER

b. Flow Blaced Simulated Thermal Power-Upecale 0.68 d2I

1) Flow Blamed 5 0.M(w-aw) *ArIt*

• with 5 O M (w-aw) M %**

a maxi ,a of with a maximum of 2)-High Flow Clamped s 113.5s of RATED $ 115.5% of RATED THERMAL POWER THERMAL POWER Fixed Neutron Flux-Upecale $ 118% of RATED THERMAL POWER S 120% of RATED y c.

THERMAL POWER s~

NA NA

d. Inoperative Reactor Vessel Steam Dome Pressure - High 5 1037 poi 9 5 1057.poig 3..

Reactor vessel Water Level - Low,' Level 3 2'12.5 inches above instrument 2 11.0 inches above 4.- zero* instrument zero s 8% closed 5 12% closed

5. Main Steam Line Isolation Valve - Closure

• 5ee Bases Figure B 3/4 3-1.

E- **The Average Power Range Monitor Scram function varies as a function of recirculation loop drive flow (w).

I Aw le defined as the difference in indicated drive flow (in percent of drive flow v51ch produces rated Aw = 0 for two recirculation core flow) between two loop 4 iingle loop operation at the same core f' .

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loop operation. Aw = 9% fot igle recirculation loop operation. l g

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. (0.58N-b + I POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS g LIMITING CONDITION FOR OPERATION (0.WW-Mw+.................

doU l 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip i setpoint (Spg) shall be established according to the following relationships:

M TRIP SETPOINT ALLOWABLE VALUE 0.58(W.-hW ) -i- 5d T S s -<e.ce:u-2u: - - s n g. S s ac.ss:u-ar:-- se:r a Sgs ( 0. S S (u-du; * - ^ 12t;T S s (0 5f("-2:?)** A m )?

where S and S aM po nent d M D T MR, l RB W = Loop recirculation flow as a percentage of the loop  !

recirculation flow which produces a rated core flow of 100 Q.dM .g.de)T million lbs/hr.

T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER i

l (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if less than or equal to 1.0. ,

APPLICABILTTY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

i ACTION:

With the APRM flow biased simulated thermal power-upscale scram trip setpoint I and/or the flow biased neutron flux-upscale control rod block trip setpoint l less conservative than the value shown in the Allowable value column for S or )

S as above determined, initiate corrective action within 15 minytes and l aku,stSand/ ors tr ,e consistent with the Trip Setpoint values within 6 )

hoursorreduceTNRMALPOWERtolessthan25%ofRATEDTHERMALPOWERwithin l the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the CMFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and flow biased neutron flux-upscale control rod block trip setpoints verified to be within the above limits or adjusted, as required:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with CMFLPD greater than or equal to FRTP.

d. The provisions of Specification 4.0.4 are not applicable.

• With CMFLPD greater than the FRTP, rather than adjusting the APRM setpoints, the APRM may be adjusted such that the APRM readings are greater than or equal to 100% times CMFLPD provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER and a notice of adjustment is posted on the reactor control panel.

• • The Average Power Range Monitor Scram function varies as a function of recirculation loop drive flow (w). Aw is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow.

Aw = 0 for two recirculation loop operation. Aw = 9% for single l recirculation loop operation.

HOPE CREEK 3/4 2-2 Amendment No. 63 l

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

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%e whe. of IE 'is Spec'Swd in ne_ Core Optmb3 -

Cvv6h Repor4. ,

TABLE 3.3.6-2 CONTROL R00 BLOCK INSTRUMENTATION SE1 POINTS g TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE 5 1. ROO BLOCK MONITOR n a. Upscale f_OMNM)N-do* go 66N-AwW @<

h Flow Blased N

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1. - 0.00 ( o.) . ;G' - 0.00 (. a.) an

" 11. High Flow Clamped N

[ I^N g <4 7 10a" < (g,yagj,' ,

b. Inoperative NA NA ~

c. Downscale > 5% of RATED THERMAL POWER > 3% of RATED THERMAL POWER

2. APRM

a. Flow Biased Neutron Flux -

4 0.5B(4 eM)+50% s. o '5 W M + W .

Upscale a MS-14 ^ 'N* _ 0. 5 E ( w- c.u ' - '5%*

b. Inoperative __NA_ _. _ A

c. Downscale ~> 4% of RATED THERMAL POWER > 3% of RATED THERMAL POWER

d. Neutron Flux - Upscale, Startup 1 12% of RATED THERMAL POWER 314%ofRATEDTHERMALPOWER

3. SOURCE RANGE MONITORS

a. Detector not full in NA NA 5

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b. Upscale < 1.0 x 10 cps < 1.6 x 10 c, '

c. Inoperative NA NA T, d. Dcwnscale -.

> 3 cps > 1.8 cps

4. INTFRMEDIATE RANGE MONITORS

a. lietector not full in MA NA

b. Upscale $ 108/125 divisions of $ 110/125 divisions of full scale full scale

c. Inoperative NA NA

d. Downscale > 5/125 divisions of > 3/125 divisions of Tull scale Tull scale

5. SCRAM DISCHARGE VOLUME

a. Water Level-High (Float Switch) 109'1" (North Volume) 109'3" (North Volume) 108'11.5" (South Volume) 109'1.5" (South Volume) k 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW til . l H'l

$ a. Upscale 1 -408%. of rated flow $ -H&-of rated f low 5 b. Inoperative A NA

f. c. Comparator i 10% flow deviation i 11% flow deviation

& 7. REACTOR MODE SWITCH SHUTDOWN POSITION NA NA 5 *The rod block function is varied as a function of recirculation loop flow (w) and Aw which is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow. The trip setting of the Average Power Range Monitor Rod Block function must be maintained in accordance with Specification 3.2.2.

__- - _____ ______ _- -_-______ - -__ -_ -__- . __ _ _ _ _ = _ __ . - _ _ _ _ - _ _ _ _ _ . _ _ _ _ - _ - _ _ - -

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ADMINISTRATIVE CONTROL 3

, .................................=............................................ l RADIOACTIVE EFFLUENT dELEASE PZPOAT (Continued) k -

The radioactive effluent release report shall also include an assessment of '

i radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor

releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 )

consecutive months to show conformance with_40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods

for calculating the dose contribution from liquid and gaseous effluents are >

given in Regulatory Guide 1.109, Rev. 1.

j The radioactive effluent release report shall include the following l 4 information for each class of solid waste-(as defined by 10 CFR 61) shipped

. offsite during the report periods e

a. Container volume,

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclide (specify whether determined by measurement or ,

i estimate), l

! d. Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),  ;

j e. Type of container (e.g., LSA, Type A, Type 3, Large Quantity), and ,

f. Solidification agent (e.g., cement, urea formaldehyde).  ;

1 j The radioactive affluent release report shall include unplanned releases from l l 1 the site to the UNRESTRICTED AREA of radioactive materiale in gaseous and ,

liquid effluents on a quarterly basis. [

j The radioactive effluent release report shall include any changes to the l j PROCESS CONTROL PROGRAM (PCP), OFFSITE DOSE CALCULATION MANUAL (ODCM) or radioactive waste systems made during the reporting period.  !

! MONTHLY OPERATING REPORTS j .. 1 I

6.9.1.8 Routine reports of operating statistics and shutdown experience shall

be submitted on a monthly basis to the U.S, Nuclear Regulatory Commission,e ,

l Document Control Desk, Washington, D.C. 20555, with a copy to the USNRC I Administrator, Region 1, no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT l

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6.9.1.9 Core operating limits shall be established and documented in the l PSEEG generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifications:

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO 3/4.2.4 LINEAR HEA~ GENERATION RATE 314.325 n --

m * "bN M"* "

HOPE CREEK 6-20 Amendment No. b7 l 1

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NLR-N94029 l LCR 94-02 1

! LCR 94-27 l LCR 94-28 l 1

ATTACHMENT'3 l

l NEDC-31487 INCREASED CORE FIDW AND EXTENDED IDAD LINE LIMIT l j ANALYSIS FOR HOPE CREEK GENERATING STATION UNIT 1 CYCLE 2 FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION l i

t DOCKET NO. 50-354 l

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