Text

Amend 54 to License NPF-57,allowing Exception to TS 4.0.4 Surveillance Requirements for IRMs & SRMs When Operational Condition 2 or 3 Is Entered from Operational Condition 1
	ML20114C082
Person / Time
Site:	Hope Creek
Issue date:	08/24/1992
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20114C083	List: ML20114C082; ML20114C090;
References
	NUDOCS 9209010165
	Download: ML20114C082 (12)
	v • d • e

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UNITED STATES l'

'3 NUCLEAR REGULATORY COMMISSION i

usmuot o9. o. c. act>t.s

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[ M LIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY QQGLLh0. 50-3M BOPE.[ REEK GENERATING STATION MiBDMENT TO FAClllTY OPERATING LICENSE Amendment No. s4 License No. NPF-57 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 May 19, 1992, as supplemented by letter dated August 5, 1992, 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; 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 3 apter 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 cf 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 54, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.

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

9209010165 920824 PDR ADOCK 05000354 PDR

. 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION f

es L.

11er, Direc r roject Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 24, 1992

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ATTACHMENT 10 llCENSE AMENDMENT NO.54 _

FAClllTY OPERATING LICENSE NO. NPF-57 DQC.KET 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.*

Eg_mgXg insert 1-11 1-11 3/4 3-1 3/4 3-1 3/4 3-2 3/4 3-2*

3/4 3-55 3/4 3-55*

3/4 3-56 3/4 3-56 3/4 3-87 3/4 3-87*

3/4 3-88 3/4 3-88 3/4 4-3 3/4 4-3*

3/4 4-4 3/4 4-4 s

TABLE 1.2 OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITION POSITION

@0LANTTEMPERATURE 1.

POWER OPERATION Run Any temperature 2.

STARTUP Startup/ Hot Standby Any temperature 3.

HOT SHUTDOWN Shutdown #'***,

> 200 F 4.

COLD SHUTDOWN Shutdown #'##'***

1 200'F S.

REFUELING

dhutdown or Refuel **'#

$ 140 F

#The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions and related instrumentation provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically quelified member of the unit technical staff.

If the reactor mode switch is placed in the Refuel position, the one-rod ~out interlock shall be OPERABLE.

1. The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.

Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

- See Special Test Exceptions 3.10.1 and 3.10.3.

- - The reactor mode switch may be placed in the Rafuel position while a single control rod is being recoupled or withdrawn provided that the one-rod-out interlock is OPERABLE.

i HOPE CREEK 1-11 Amendment No.54 1

m 3/4.3 INSTRUMENTATICN 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY:

As shown in Table 3.3.1-1.

ACTION:

I With the number of OPERABLE channels less than required by the Minimum a.

OPERABLE Channels per Trip Sy/or that trip system in the tripped condi stem requirement for one trip system, place the inoperable channel (s) and tion

within twelve hours.

The provisions of Specification 3.0.4 are not applicable.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System reqJirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REOL'IREMENTS 4.3.1.1 Each reactor protection system instrumentat3 inel shall be demonstrated OPERABLE by the performance of the CHANNL stick, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4. 3.1. 2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 munths.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where P is the total number of redundant channels in a specific reactor trip system.

4.3.1 4 The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2 or 3 from OPERATIONAL CONDITION 1 for the Inter-mediate Range Monitors.

"An inoperable channei need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

- If more channels are inoperabie in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function to occur.

HOPE CREEK 3/4 3-1 Amendment No. 54

TABLE 3.3.1-1 g

E REACTOR PROTECTION SYSTEM INSTRUMENTATION 9

m" APPLICA8LE N!NIMUM l

i OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)

ACTION 1.

Intermediate Range Monitors (h).

a.

Neutron Flux - High 2

3 1

3' 4(c) 2(d) 2 5

3 3

b.

Inoperative 2

3 1

3, 4 2(d) 2 5

3 3

R

'2.

Average Power. Range Monitor '):

I a.

Neutron Flux - Upscale, Setdown 2

2 1

2 U

5(c) 2(d) 3 n,

b.

Flow Blae.ed Simulated Themal Power - Upscale 1

2 4

c.

Fixed Neutron Flux. Upscale 1

2 4

d.

Inoperative 1, 2 2

'l 3, 4 2(d-)

2 gc) 5 2

3 3.

Reactor Vessel Steam Dome Pressure - High 1, 2(g) 2 1

4.

Reactor Vessel Water Level - Low, g

Level 3 1, 2 2

1

.5.

S.

Main Steam Line Isolation Valve -

I9) 4 4

g Closure I

l E.

~

\\

o 5'

A TABLE 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CMANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNITS CHECK TEST CALIBRATION a.

Reactor Vessel Water level -

Low Low, Level 2 5

M R

b.

Reactor Vessel Water S

M R

tevel - High, level 8 l

c.

Condensate Storage Tank i

Level - Low NA M

R I

"1 d.

Manual Initiation NA M('a)

MA

~

y (a) Manual initiation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once l

per 31 days as part of circuitry required to be tested for automatic system actuation.

INSTRUMENTATION 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTA'ivN LIMITING CONDITION FOR OPERATION 3.3.6.

The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

a.

With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restoredtoOPERABLEstatuswithitstripsetpointadjustedconsistent j

with the Trip Setpoint value, b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.

SURVEILQNCEREQUIREMENTS 4.3.6 Each of the above required control rod block trip systems and instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.

The provisions of Specification 4.0.4 are not applicable for entry into OPER-ATIONAL CONDITION 2 from OPERATIONAL CONDITION 1 for the Source Range Monitors or the Intermediate Range Monitors.

HOPE check 3/4 3-56 Amendment No. 54 l

l

~

5 TAalf 1.3.7.5-1 k

ACCIDLNi MONITORING INSTFtM[NI AIION SURVIIli ANCL RIQUIRf M[NTS m

APPLICABLE Q

CilANN[ t CIENNI I OPERAIIONAL INSTRt#ENT Clit CK cat 1BRAIION CONDIiIONS 1.

Reactor Vessel Pressure M

R 1,2,3 4

2.

Reactor Vessel Water Level M

R 1,2,3 3.

Suppression Chamber Water Level M

R 1,2,3 4.

Suppression Chamber Water Temperature M

R 1,2,3 5.

Suppression Chamber Pressure M

R 1,2,3 a

6.

Dryw11 Pressure M

R I,7,3 7.

Drywell Air Temperature M

R I,7,3 8.

Primary Containment Hydrogen /0xygen Concentration Analyzer and Monitor M

q' g,7,3

)

2; 9.

Safety / Relief Valve Position Indicators M

R 1,7,3 10.

Drywell Atmosphere Post-Accident Radiation Monitor M

R**

1,7,3 0

11.

North Plant Vent Radiation Monitori M

R 1,2,3 e

12.' South Plant Vent Radiation Monitori M

R 1,2,3

13. FRV5 Vent Radiation Monitorf M

R 1,7,3 14.' Primary Containment Isolation Valve Position Indication M

'?

1,2,3 "Using sample gas containing:

a. Five volm percent oxygen balance nitrogen (oxygen analyrer channel).

b. Five volume percent hydrogen, balance nitrogen (hydrogen analyser thannel).

- CHAlWIEL CAtl8AATION shall consist of an eit-ctronic calibration of the thannel, not inclinding the detecto.

l for range decades above 10 R/hr and a one point calibration check of tfie detector below 10 R/hr with an i

installed or pcrtable gamma source.

High range noble gas monitors.

l L

INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

a.

In OPERATIONAL CONDITION 2*,

three, b.

In OPERATIONAL CONDITION 3 and 4, two.

APPLICABILITY:

OPERATIONAL CONDITIONS 2*j 3 and 4.

ACTION:

a.

In OPERATIOuAL CONDITION 2* with one of the above required source range moni'.. channels inoperable, restore at least 3 source range monitor enannels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Snutdown position within one hour.

SUDVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source ra ge monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per:

1 a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION 2*, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 18 months.

l b.

Performance of a CHANNEL FUNCTIONAL TEST:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months p ior to moving the reactor mode switch from

(

the Shutdown position, if nct performed within the previous 7 days, and 2.

At least on u per 31 days.

c.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 3 cps with the detector fully inserted.

d.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 2* or 3 from OPERATIONAL CONDITION 1.

~~

"With IRM's on

. ge 2 or below.

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

HOPE CREEK 3/4 3-83 Amendment No. 54 L

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i REACTOR COOLANT SYSTEM JET PUMPS LIMITING CONDITION FOR OPERATION j

3.4.1.2 All jet pumps sh611 be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

I With one or more jet pumps inoperable, be in at least HOT SNUTDOWN within i

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENT;*

i 4.4.1.2 All jet pumps shall be demonstrated OPERABLE as follows:

a.

Each of the above required jet pumps shall be demonstrated OPERABLE i

prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER and at i

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by determining recirculation loop flow, total core flow and diffuser-to-lower plenum differential pressure for each i

jet pump and verifying that no two of the following conditions occur when the recirculation aumps are operating in accordance with Specification 3.4.1.3.

The indicated recirculation loop flow differs by more than 10%

1.

from the established pump speed-loop flow characteristics.

2.

The indicated total core flow differs by more than 10% from the established total core flow value derived from recirculation loop flow measurements.

3.

The indicated diffuser-to-lower plenum differential pressure of any individual jet pump differs from the established patterns by more than 10%.

b.

During single recirculation loop operation, each of the above required jet pumps shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that no two of-the following conditions occur:

l 1.

The indicated recirculation loop flow in the operating loop dif-l fers by more than 10% from the established

pump speed-loop flow l

characteristics.

(

2.

The indicated total core flow differs by more than 10% from the i

established

total core flow value derived from sint recirculation loop flow measurements.

l 3.

The indicated diffuser-to-lower plenum differential pressure l

l of any individual jet pump differs from estab1 k hed* single recirculation loop patterns by more than 10%.

c..

The provisions of Specificction 4.0.4 are not applicable provided that this surveillance is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding 25% of RATED THERMAL POWER.

"During startup following any refueling outage and in order to obtain sir.gle loop or two loop operation baseline data, data shall be recorded for the parameters listed to provide a basis for estab.shing the specified relationships.

Com-parisons of the actual data in accordance with the criteria listed shall commence upon conclusion of the baseline data analysis.

i HOPE CREEK 3/4 4-4 Amendment No.54

.

ML20114C082

Text

Attachment:

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