Text

Amend 63 to License NPF-57,extends Period of Time to Reduce Setpoints of APRM & RBM When Plant Enters SLOs
	ML20059L117
Person / Time
Site:	Hope Creek
Issue date:	01/25/1994
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20059L121	List: ML20059L117; ML20059L122;
References
	NUDOCS 9402030189
	Download: ML20059L117 (19)
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UNITED STATES j.

j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20555-0001 g

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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. NPF 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company (PSE&G) dated February 2, 1993 and supplemented by letter dated November 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; 1

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment'to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

(2) Technical Soecifications and Environmental Protection Plan The Technical' Specifications contained in Appendix A, as revised through Amendment No. 63, and the Environmental Protection Plan contained in Appendix B, are.hereby incorporated into the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

9402030189 940125 PDR-ADOCK 05000354 P

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. 3.

The license amendment is effective as of its.date of issuance, and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ad. I mL Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 25, 1994 I

o ATTACHMENT TO LICENSE AMENDMENT N0.

FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with.

the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.*

Remove Insert 2-3 2-3*

2-4 2-4 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2*

3/4 2-1 3/4 2-1*

i 3/4 2-2 3/4 2-2 3/4 4-1 3/4 4-1 3/4 4-2 3/4 4-2 j

i 3/4 4-2a 3/4 4-2a

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3/4 4-2b 3/4 4-2b B 3/4 0-3 B 3/4 0-3*

B 3/4 0-4 B 3/4 0-3a B 3/4 0-4 B 3/4 4-1 8 3/4 4-1 B 3/4 4-2 B 3/4 4-2*

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4 SAFET* LIMITS AN* LIMIT!NS SAFETi SYSTEM SETTINGS

2. 2 t!MITING Sariin SYS*EM SETTINGS REACTCR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reacte protection system irstrumentation setpoints shall.be set.

consistent with the Trip Setpoint values.shown in Table 2.2.1-1.

1 Appt1CABit1Tv: As shown in Table 3.3.1-1.

ACTION:

With a reactor protection. system. instrumentation setpoint less conservative.

than the value shown in the Allowable Values column of. Table 2.2.1-1, ceclare-the channel inoperable and apply the applicable ACTION statement reQuiremert of Specification 3.3.1 until the channel is restored to OPERABLE status wit -

its setpoint acjustec consistent with the Trip Setpoint value.

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4 HOPE CREEK 2-3

TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS

to FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

O 1.

Intermediate Range Monitor, Neutron Flux-High 5 120/125 divisions s 122/125 divisions h

of full scale of full scale X

2.

Average Power Range Monitor:

a.

Neutron Flux-Upscale, Setdown s 15% of RATED THERMAL POWER s 20% of RATED TPERMAL POWER b.

Flow Blased Simulated Thermal Power-Upscale

1) Flow Biased s 0.66(w-Aw)+51t** with s 0.66(w-Aw)+54t**

a maximum of with a maximum of

2) High Flow Clamped 5 113.5% of RATED s 115.5% of RATED THERMAL POWER THERMAL POWER y

c.

Fixed Neutron Flux-Upscale s 118% of RATFS THERMAL POWER s 120% of RATED l

THERMAL POWER d

l d.

Inoperative NA NA 3.

Reactor Vessel Steam Dome Pressure - High 5 1037 psig s 1057 peig

~

4.

Reactor Vessel Water Level - Low, Level 3 2 12.5 inches above instrument 2 11.0 inches above zero*

instrument zero 5.

Main Steam Line Isolation Valve - Closure s 8% closed s 12% closed g

See Bases Figure B 3/4 3-1.

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

y Aw is defined as the difference in indicated drive flow (in percent of drive flow which produces rated

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core flow) between two loop and single loop operation at the same core flow.

Aw = 0 for two recirculation.

94 for single recirculation loop operation.

l loop operatton.

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3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION

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3.0.1 Compliance with the Limiting Conditions for Operation contained in the

.i succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting condition for Operation is restored prior to expiration of the specified time intervals, completion of the Action requirements is.not required.

3.0.3 When a Limiting condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, ins 1.

At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

.I 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and' 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL CONDITIONS 4 or 5.

3.0.4 Entry into ars OPERATIONAL CONDITION or other specified condition shall not be made when che conditions for the Limiting Condition for Operation are not met and thr, associated ACTION requires a shutdown if-they are not met within a specified time interval.

Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.

3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be. returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of I

other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

i HOPE CREEK 3/4 0-1 Amendment No. 63 l

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APPLICABILITY SURVEILLANCE REQUIREMENTS

4. 0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS..

or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within its specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condi-tion shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:

Inservice inspection of ASME Code Class 1, 2, and 3 components and a.

inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)

(6) (1).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and HOPE CREEK 3/4 0-2 Amendment No. 37 APR 3 1590

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits specified in the CORE OPERATING LIMITS REPORT.

The limits specified in the CORE OPERATING LIMITS REPORT shall be reduced to a value of 0.86 times the two recirculation loop operation limit when in single recirculation loop operation.

APPLICABILITY:

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

ACTION:

With an APLHGR exceeding the limits specified in the CORE OPERATING LIMITS REPORT, initiate corrective action within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the limits specified in the CORE OPERATING LIMITS REPORT:

l a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when.the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.

d.

The provisions of Specification 4.0.4 are not applicable.

HOPE CREEK 3/4 2-1 Amendment No. 34 UCf 2 01989

POWER DISTRIBUTION LIMITS i

3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 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.

setpoint (Spg) shall be established according to the following relationships:

TRIP SETPOINT ALLOWABLE VALUE S s (0.66(w-Aw)** + 51%)T S s (0.66(w-Aw)** + 54%)T S

s (0.66(w-Aw)**+ 42%)T

.S s (0.66(w-Aw)** + 45%)T where SkndS n pemnt d MD Tb NR, M

RB W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 100 million lbs/hr.

T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY (CMFLPD). T is applied only if less than or equal to 1.0.

APPLICABILITY:

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

ACTION:

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

as above determined, initiate corrective action within 15 mingtes and abhu,stSand/ ors to be consistent with the Trip Setpoint values within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sorreduceTkbRMALPOWERtolessthan25%ofRATEDTHERMALPOWERwithin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 samo 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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J/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION

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3.4.1.1 Two reactor coolant system recirculation loops shall be in operation with:

a.

Total core flow greater than or equal to 45% of rated core flow, or b.

THERMAL POWER less than or equal to the limit specified in Figure 3.4.1.1-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2".

ACTION:

a.

With one reactor coolant system recirculation loop not in operation:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months a)

Place the recirculation flow control system in the Local Manual-mode, and b)

Reduce THERMAL POWER to 5 70% of RATED THERMAL POWER, and c)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit' by 0.01 to 1.08 per Specification 2.1.2, and d)

Reduce the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit to a value of 0.86 times the two recirculation loop limit per Specification 3.2.1, and e)

DELETED.

l f)

Limit the speed of the operating recirculation pump to less than or equal to 90% of rated pump speed, and g)

Perform surveillance requirement 4.4.1.1.2 if THERMAL POWER is s 38% of RATED THERMAL POWER or the recirculation loop flow in the operating loop is s 50% of rated loop flow.

2.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the Average Power Range Monitor (APRM)

Scram Trip Setpoints and Allowable values to those applicable for single recirculation loop operation per Specifications 2.2.1 and 3.2.2; otherwise, with the Trip Setpointe and Allowable Values associated with one trip system not reduced to those. applicable for single recirculation loop operation, place the affect *4 trip system in the tripped condition'and within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , reduce the Trip Satpoints and Allowable-Values of the affected channels to those applicable for single recirculation loop operation per Specifications 2.2.1 and 3.2.2.

3.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the APRM Control Rod Block Trip See Special Test Exception 3.10.4.

l HOPE CRFEK 3/4 4-1 Amendment No. 63 l'

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REACTOR COOLANT SYSTEM ACTION (Continued)

Setpoints and Allowable Values to those applicable for single recirculation loop operation per Specifications 3.2.2 and 3.3.6; otherwise, with the Trip Setpoint and Allowable Values associated with one trip function not reduced to those applicable for single recirculation loop operation, place at least one affected channel in the tripped condition and within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , reduce the Trip setpoints and Allowable values of the affected channels to those applicable for single recirculation loop operation per Specifications 3.2.2 and 3.3.6.

4.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , reduce the Rod Block Monitor Trip Setpoints and Allowable Values to those applicable for single recirculation-loop operation per Specification 3.3.6; otherwise, with the Trip setpoints and Allowable values associated with one trip function not reduced to those applicable for single recirculation loop operation, place at least one affected channel in the tripped condition and within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , reduce the Trip setpoints and Allowable values of the remaining channels to those applicable for single recirculation loop operation per Specification 3.3.6.

5.

The provisions of Specification 3.0.4 are not applicable.

l 6.

Otherwise be in at least u^T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

With no reactor coolant system recirculation loops in operation, immediately initiate action to reduce THERMAL POWER to less than or equal to the limit specified in Figure 3.4.1.1-1 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and initiate measures to place the unit in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one or two reactor coolant system recirculation loops in operation and total core flow less than 45% but greater than 40%

l of rated core flow and THERMAL POWER greater than the liniit specified in Figure 3.4.1.1-1:

j 1.

Determine the APRM and LPRM noise levels (Surveillance 4.4.1.1.4):

a)

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and b)

Within 30 minutes after the completion of a THERMAL POWER increase of at-least 5% of RATED THERMAL POWER.

1 2.

With the APRM or LPRM neutron flux noise levels greater than three times their established baseline noise j

Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

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

e REACTOR COOLANT SYSTEM ACTION (Continued) i

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levels, within 15 minutes initiate corrective action to restore the noise levels to within the required limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by increasing core flow to greater than 45% of rated core flow or by reducing. THERMAL POWER to less than or equal to the limit specified in Figure 3.4.1.1-1.

d.

With one or two reactor coolant system recirculation loops in operation and total core flow less than or equal to 40% and l

THERMAL POWER greater than the limit specified in Figure 3.4.1.1-1, within 15 minutes initiate corrective action to reduce THERMAL POWER to less than or equal to the limit specified in Figure 3.4.1.1-1 or increase core flow to greater than 40% within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l SURVEILLANCE REQUIREMENTS 4.4.1.1.1 With one reactor coolant system recirculation loop not in operation at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months verify thats a.

Reactor THERMAL POWER is s 70% of RATED THERMAL POWER, and b.

The recirculation flow control system is in the Local Manual mode, and c.

The speed of the operating recirculation pump is less than or equal to 90% of rated pump speed, and d.

Core flow is greater than 40% when THERMAL POWER is greater than the l

limit specified in Figure 3.4.1.1-1.

4.4.1.1.2 With one reactor coolant system recirculation loop not in operation, within no more than 15 minutes prior to either THERMAL POWER I

increase or recirculation loop flow increase, verify that the following differential temperature requirements are met if THERMAL POWER is s 38% of l

RATED THERMAL POWER or the recirculation loop flow in the operating recirculation loop is s 50% of rated loop flow:

l a.

s 145'F between reactor vessel steam space coolant and bottom head drain line coolant, and b.

s 50*F between the reactor coolant within the loop not in operat ion and the coolant in the reactor pressure vessel, and c.

s 50*F between the reactor coolant within the loop not in operatton and the operating loop.

The differential temperature requirements or Specifications 4.4.1.1.2b and 4.4.1.1.2c do not apply when the loop not in operation is-isolated from the reactor pressure vessel.

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

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.1.1.3 Each pump MG set scoop tubo mechanical and electrical stop shall be demonstrated OPERABLE with overspeed setpoints less than or equal to 109% and 107%, respectively, of rated core flow, at least once per 18 months.

4.4.1.1.4 Establish a baseline APRM and LPRM neutron flux noise value within the regions for which monitoring is required (Specification 3.4.1.1, ACTION c) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of entering the region for which monitoring is required unless baselining has previously been performed in the region since the last refueling outage.

Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

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

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I 3/4.0 APPLICABILITY l

BASES (Con't)

- t a lower' CONDITION of operation.is reached in less. time than allowed, the total allowable time to reach COLD SHUTOOWN,: or other OPERATIONAL CONDITION, is not.

reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed'to-reach HOT SHUTD0WN is the next 11_ hours because the total time to reach'HO SHUTDOWN is not reduced _from the allowable Ifeit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore. if remedial measures are completed that would permit'a return to POWER operation,.

i a penalty is not incurred by having to reach a lower CONDITION of operation in i

less than the total time allowed.

The same principle applies with regard to the allowableLoutage time limits of-the ACTION requirements, if complianc's with the ACTION requirements;for one

. 1 specification results in entry into an OPERATIONALCONDITION or condition of operation for another specification in which the requirements of the Limiting-l Condition for Operation are not met.

If the new specification becomes'appli,

cable in' less time than~ specified, the difference may be added Lto the allowable outage time limits of.the second specification.

However, the, allowable outage, time limits of ACTION requirements for a higher CON 0! TION of operation may not be-used to extend the allowable outage time that is applicable when a Limiting;

- i Condition for Operation is not est in a-lower CONDITION of' operation.

~

I' The shutdown-requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial seasures to.be taken.

j Specification 3.0.4establisheslimitationsonachangeinIOPERATIONALCONDI-TIONS wnen a Limiting Condition for Operation is not met.- It precludes placing

j the facility in a higher CO MITION of operation.when the requirements.for a Limiting Condition for Operation are not met and continued noncompliance to 3

these conditions would resule in a shutdown to comply with. the ACTION require -

monts if a change in CONDITIONS'were permitted.

The purpose of_ this specif1-cation is to ensure that facility operation is not-initiated or that higher CONDITIONS'of operation are not entered when corrective action is being:taken to obtain compliance with a specification by restoring equipment'to OPERA 4LE status or parameters to specified limits., Compliance with ACTION requirements.

that permit continued. operation'of the facility for an unlietted period of. time provides an acceptable level of safety for continued operation without regard ~

to the status of'the plant before or after a change in OPERATIONAL CONDITIONS.

Therefore, in this case,_ entry into'an OPERATIONAL' CONDITION or other specified condition may.be'made in accordance with the provisions of the ACTION reouire-ments.

The. provisions of Lthis specification should _not, however, be inter-preted as endorsing the failure to exercise good practice in restoring syntaes-or components to 0PERA8LE. status before plant startup..

1 When a shutdown is required to comply with ACTION requirements, the provisions

.l of Specification 3.0.4 do not apply.because they would dalay placing the facility in a lower CONDITION of operation.

j HOPE' CREEK 8 3/4 0-3 Amendment No. 19 '

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4 3/4.0 APPLICABILITY BASES (Continued)

..............................................=...............................

Soecification 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of.this Specification-is to provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Requirod Action (s)) to allow the performance of testing required to restore and demonstrates a.

The OPERABILITY of the equipment being returned to service; or b.

The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the testing required to restore and demonstrate the OPERABILITY of the cquipment. This Specification does not provide time to perform any other preventative or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the testing required to restore and demonstrate OPERABILITY.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of testing required to restore OPERABILITY of another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of testing required to restore and demonstrate the OPERABILITY on another channel in the same trip system.

LCO 3.0.5 is applicable to all Technical Specifications; however, the intent of LCO 3.0.5 is not to supersede more specific guidance contained within any individual specification.

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HOPE CREEK B 3/4 0-3a

' Amendment No. n3 l

i 0

3/4.0 APPLICABILITY BASES (Con't)

Specifications 4.0.1 through 4.0.5 establish the general requirements appli-cable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is 1

maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and' components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to f acilitate surveillance s-%duling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.

The ifmitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillancp being performed is the verification of conformance with the Surveillance Requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perform a Surveillance Require-ment within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to HOPE CREEK B 3/4 0-4 Amendment No. 37 APR 3 1990

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3/4.4 REACTOR COOLANT SYSTEM BASES

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3/4.4.1 RECIRCULATION SYSTEM The impact of single recirculation loop operation upon plant' safety is assessed and shows that single loop operation is permitted if the MCPR fuel' cladding safety Limit is increased as noted by Specification 2.1.2, APRM scram and control rod block setpoints are adjusted as noted in Tables 2.2.1-1 and 3.3.6-2 respectively. MAPLHGR limits are decreased'by the factor given in Specification 3.2.1, and MCPR operating limits are adjusted per Specification 3/4.2.3.

Additionally, surveillance on the pump speed of the operating recirculation loop is imposed to exclude the possibility of excessive core internals vibration. The surveillance on differential temperatures below 38%

THERMAL POWER or 50% rated recirculation loop flow is to mitigate the undue thermal stress on vessel nozzles, recirculating pump and vessel bottom head during the extended operation of the single recirculation loop mode.

An inoperable jet pump is not in itself a sufficient reason to declare a recirculation loop inoperable, but it does, in case of a design-basis-accident, increase the blowdown area and reduce the capability of reflooding the core, thus, the requirement for shutdown of the facility with a jet pump inoperable. Jet pump failure can be detected by monitoring jet pump performance on a prescribed schedule for significant degradation.

Recirculation loop flow mismatch limits are in compliance with the ECCS LOCA analysis design criteria for two recirculation loop operation.

The limits will ensure an adequate core flow coastdown from either recirculation loop following a LOCA.

In the case where the mismatch limits cannot be maintained during two loop operation, continued. operation is permitted in a single recirculation loop mode.

In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50*F of each other prior to startup of an idle loop. The loop temperature must also be within 50'F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles.

Sudden equalization of a temperature difference > 145"F between the reactor vessel bottom head coolant and the coolant in the upper region of the reactor vessel by increasing core flow rate would cause undue stress in the reactor vessel bottom head.

The objective of GE BWR plant and fuel design is to provide stable operation with margin over the normal operating domain.

However, at the high power / low flow corner of the operating domain, a small probability of. limit cycle neutron flux oscillations exists depending on combinations of operating conditions (e.g., rod pattern, power shape). To provide assurance that neutron flux limit cycle oscillations are detected and suppressed, APRM and LPRM neutron flux noise levels should be monitored while operating in this region.

HOPE CREEK B 3/4 4-1 Amendment No. 63 l

g 4

3/4.4 REACTOR COOLANT SYSTEM SA5ES 5taoility tests at operating BWRs were reviewe region of the power / flow map in which surveillance d to determine a generic shoulo be performed.

for determining the generic region for survefilance to acco plant variability of cecay ratio with core and fuel designsr the Diant to has been determined to corre5Dond to a core flow of less than or eThis generic re of rated core flow and a THERMAL POWER greater than that specifie qual to 45%

3.4 1.1-1.

region for monitoring neutron flux noise levels. Plant specific calcu t

1 e

In this case the degree of conservatism can be reduced since plant to plant variability would be eliminat; In this case, adecuate margin will be assured by monitoring the region wh a decay ratio greater than or equal to 0.8.

has Neutron flux of limit cycle neutron flux oscillations. noise limits are also established to ensure l

neutron flux noise caused by. random boilin BWR cores typically operate with flux noise levels of 1-12%.of rated power (g and flow noise. Typical neutron recirculation loop operation.the range of low to high recirculation loop flow ual Neutron flux noise levels which significantly bound these values are considered in the thermal / mechanical design of G t

fuel and are found to be of negligib'e consequence at optrating BWRs have demonstrated that when stability related neutron fluxIn a

~

limit cycle oscillations occur they result in peak-to peak neutron flu cycles of 5-10 times the typical values.

x limit Therefore. actions taken to reduce i

neutron flux noise levels exceeding three (3) times the typical value are suf-ficient to ensure early detection of limit cycle neutron flux oscillations.

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magnitude as core flow is increased (constant control ro reactor recirculation loops in operation. Therefore, the baseline neutron flux noise level obtained at a specific core flow can be applied over a~ range of flows.

of the flow range, the range over which a specific baseli

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exceed 20% of rated core. flow with two recirculation loops in operation.

from tests and operating plants indicate that a range of 20% of rated core fl Data will result in approximately a 50% increase in neutron flux noise level'durin o-operation with two recirculation loops.

Baseline data should be taken near.-the g

. maximum rod line at which the majority of operation will occur.

vative value since the neutron flux noise level is propo

. However, base-i r-level at a given core flow.

a l

3/4.4.2 SAFETY / RELIEF VALVES the reactor coolant system from~being pressurized above k

I 1375 psig in accordance with the ASME Code.

A total of 13 OPERABLE safety /relie' HOPE CREEK B 3/4 4-2 Amendment No.

3-APR 7.

1987 9 *--

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ML20059L117

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