ML20034A581

Amend 3 to License NPF-85,allowing Required Source Range Monitor Count Rate to Be Reduced While Ensuring That Design Level of Counting Certainty Maintained at All Times for Source Range Monitors

ML20034A581
Person / Time
Site:	Limerick
Issue date:	04/09/1990
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034A576	List: ML20034A575 ML20034A581 ML20034A582
References
NUDOCS 9004230518
Download: ML20034A581 (12)

Text

- _ -

t.,*

d flo

/'gIo.,

UNITED STATES

[,

g NUCLEAR REGULATORY COMMISSION-

,j WASHINGTON. D, C,20666

\\...../

PHILADELPHIA ELECTRIC COMPANY

. DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2.

AMENDMENT TO FACILITY OPERATING LICENSE ~

Amendment-No. 3 License No NPF 1.

The Nuclear Regulatory Comission (the Comission) has found 'that A.

The application for amendment by Philadelphia Electric Company (the-licensee) dated January 29, 1990,. complies'with the standardso 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 1;.

B.

The. facility wi11' operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations;:

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.Comission'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-85 is hereby' amended to read as follows:'

A Technical Specifications d

1 The Technical Specifications contained in Appendix A and the-Environmental Protection Plan contained in Appendix B, as: revised.

Ti through Amendment No. 3 are hereby incorporated into this y

license. Philadelphia Electric Company shal1~ operate the' facility.

4 in accordance with the Technical Specifications and the Environmental Protection Plan.

(;;

h P

't

~

. :k.

3.

This license amendment is effective as of its'date~ of. issuance.

FOR THE NUCLEAR. REGULATORY COMMISSION l

Isl

' Walter R. Butler, Director Project Directorate 1-2 Division.of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications-

.Date of Issuance:

April 9, 1990

.{

Jj I

i l

]

1 i

v

.h #?

N LL y#.e# gb,~ [s '

PDI-2/Pdd OGC PDI-2/D A

en RClark:fr7 WBut}er g/

a 90 d3 //f/90

/ /90 d,/3/90

2-

l. - !.

i 3.

This license amendment is effective as of its date:of issuance.

.L

'j-FOR THE NUCLEAR REGULATORY COMMISSION' J

.i L

I' Walter R. Butler, Director 1

Project Directorate I-2 j

Division of Reactor Projects.1/11-

.i L

s

Attachment:

Changes to the Technical Specifications Date of Issuance: April 9, 1990 t

O j

.i 4

t i

1

.l

-l: '

i

+

4 ATTACHMENT T0 LICENSE AMENOMENT NO. 3 FACILITY OPERATING' LICENSE N0. NPF-85' DOCKET NO. 50-353~

t e

u Replace the following pages of the Appendix A. Technical Specifications with

- the attached page. The revised pages-are identified by Amendment number and-

. contain vertical. lines indicating the area of change. Overleaf pages are provided to maintain document' completeness.*

Remove Insert vii vii*

viii viii 3/4 3-60a 3/4 3-60a' i

3/4 3-60b 3/4 3-87 3/4 3-87*

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

'l i

3/4 9-3 3/4 9-3*

3/4 9-4 3/4 9-4 i

i l

' t

-~ i t

i 9

+

9 n.

' INDEX,

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

{

SECTION PAGE I

3 INSTRUMENTATION (Continued) 3/4.3.2-ISOLATION' ACTUATION INSTRUMENTATION.....................

3/4 3-9~

Table 3.3.2-1 Isolation Actuation Instrumentation.

3/4 3'-11 Table 3.3.2-2 Isolation Actuation i

Instrumentation Setpoints...........

3/4 3-18 Table 3.3.2-3-' Isolation System-Instrumentation-.

Response Time......................

3/4 3-23' Table 4.3.2.1-1 Isolation Actuation Instrumentation Surveillance Requirements..........

3/4 3-27 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION-INSTRUMENTATION..............................-...........,

3/4 3-32 Table 3.3.3-1 Emargency Core Cooling System

. Actuation Instrumentation...........

3/4-3-33 l

Table 3.3.3-2 Emergency Core Cooling System Actuation Instrumentation Setpoints.-

.3/4 3-37 i

Table 3.3.3-3 Emergency Core Cooling System

)

Response Times.

3/4 3-39 Table 4.3.3.1 Emergency Core Cooling System-Actuation Instrumentation Surveillance Requirements.........

3/4 3-40 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION' INSTRUMENTATION' l

ATWS Recirculation Pump Trip' System Instrumentation.'....

3/4 3-42 Table 3.3.4.1-1 ATWS Recirculation Pump Trip.

System Instrumentation............

3/4'3-43~

Table 3.3.4.1-2 ATWS Recirculat. ion Pump Trip System Instrumentation Setpoints.........................

3/4 3-44

' l Table 4.3.4.1-1 ATWS Recirculatioil Pump Trip Instrumentation Surveillance

.o Requirements......................

3/4 3-45 End-of-Cycle Recirculation Pump Trip System 3

Instrumentation.........................................

3/4 3 '

1 i

LIMERICK - UNIT 2 vii 1

~

INDEX f

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

SECTION, FAGE INSTRUMENTATION (Continued) q Table 3.3.4.2-1 End-of-Cycle Recirculation Pump Trip System Instrumentation.......

3/4 3 Table 3.3.4.2-2 End-of-Cycle Recirculation Pump Trip Setpoints.....................-

3/4:3-49 R

Table 3.3.4.2-3 End-0f-Cycle Recirculation Pump Trip System-Response Time.........

3/4 3-50 1

Table 4.3.4.2.1-1 End-0f-Cycle Recirculation Pump. Trip System Surveillance.

.3/4'3-51.

Requirements....................

i 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................

3/4 3-52.

Table 3.3.5-1 Reactor-Core Isolation Cooling 3

System Actuation Instrumentation....

3/4.3-53 i

Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation

~Setpoints...........................

3/4 3-55 i

Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements..........

3/4.3-56 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION.......................

3/4'3-57 Table 3.3.6-1 Control Rod Block Instrumentation...

3/4.3-58 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints...........................

3/4 3-60 Figure 3.3.6-1 SRM Count Rate Versus Signal-to-Noise Ratio...............

3/4 3-60b Table 4.3.6-1 Control Ro'd Block Instrumentation Surveillance Requirements...........

3/4-3-61 3/4.3.7 MONITORING INSTRUMENTATION I

Radiation Monitoring Instrumentation.....................

3/4 3 Table 3.3.7.1-1 Radiation Monitoring Ins trumentati on...................

3/4 3-64 i

LIMERICK - UNIT 2 viii Amendment No. 3

.7 TABLE 3.3.6-2 (Continued) r-g CONTROL R00 BLOCK INSTRUMENTATION SETPOINTS E

7 TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE E

4.

INTERMEDIATE RANGE MONITORS Q

a.

Detector not full in N.A.

N.A.

b.

Upscale

< 108/125 divisions of

< 110/125 divisions of m

Tull scale Tull scale c.

Inoperative N.A.

N.A.

d.

Downscale

> 5/125 divisions of full

> 3/125 divisions of full icale scale 5.

SCRAM DISCHARGE VOLUME a.

Water Level-High 5 257' 7 3/8" elevation ***

$ 257' 9 3/8" elevation a.'

Float Switch 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW w

J, a.

Upscale

< 111% of rated flow-

< 114% of rated flow

?

b.

Inoperative R.A.

H.A.

c.

Comparator

-5 10% flow deviation

... 511% flow deviation 7.

REACTOR MODE SWITCH SHUTDOWN' POSITION N.A.

N.A.

E

• The rod block function varies'.as a function of recirculation. loop; drive flow (W). The trip setting of.

m E

the average power range monitor rod block' function must be maintained in accordance with Specification Pn 3.2.2.

s

.co

• • May be reduced, provided the source range monitor has an observed count rate and signal-to-noise ratio on z

or above the curve shown,in Figure 3.3.6-1.

1

• • • Equivalent to113.56 gallons / scram discharge volume.

9 I

a a

.w',*

4

-r.

p_-

..e w-e,-

f.ver swa r.-cM.-.v

9 gr.--

y e,e y

ww tr

+.

gy.w*y g g--

+

Ai

3.0 2.8 2.6 2.4 g 2.2 i

i c.

l l

w 2.0 i

e I

l i

i i

l i

l

1.8 i

i I

a o

i

$1.6 l

l l

l 1

z*

l i

i 1.4

\\

i 1.2 I

l I

I i

l 1

0.8 i

0.6,,,,,,,.,,,,,.,,

2 4

6 8

10 12 14 16 18 20 22 24 26 28 30 SIGN AL-TO-N OISE R ATIO SRM COUNT R ATE VERSUS SIGN AL-TO-NOISE R ATIO Figure 3.3.6-1 LIMERICK - UNIT 2 3/4 3-60b Amendment tio. 3 i

.a TABLE 4.3.7.5-1 y

g I

3 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREfENTS E

?

CHAlelEL CHAf80EL INSTRUMEMI CHECK CALIBRATIOff 1.

Reactor Vessel Pressure M

R

[

2.

Reactor Vessel Water Level M

R 3.

Suppression Chamber Water Level M

R j

4.

Suppression Chamber Water Temperature M

R 5.

' Suppression Chamber Air Temperature M

R 6.

Primary Containment Pressure M

R 7.

Drywell Air-Temperature M

R q#

8.

Drywell Oxygen Concentration-Analyzer M

9.

Drywell Hydrogen Concentration Analyzer M

Q*

y 10.

Safety / Relief Valve Position Indicators M

R O

11.

Primary Containment Post LOCA Radiation Monitors M

R**

12.. North Stack Wide Range Accident' Monitor ***

M R

13.

Neutron Flux-M R

.2

• Using calibration gas containing:.

a.

Zero volume percent hydrogen, balance nitrogen.

b.

five volume percent hydrogen, balance nitrogen.

• • CHANNEL Call 8 RAT 10N shall consist of an electronic' calibration of the channel, not including the detector,'

for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed.or portable gamma source.

• • • High range _ noble gas. monitors.

1. Usingfcalibration gas containing:

a.

Zero volume percent oxygen, balance nitrogen..

b.-Fivevolumelpercentoxygen, balance' nitrogen.

.. ~. -

- - - ~

, - - ~ ~ - - -

~e

- - - - - ~ - - - ~ - - - - - ' -

- - ^ ^ ^ ~ - -

3 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*#, 3, and 4.

ACTION:

a.

In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least three source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 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 Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a.

Performance of a:

1.

CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*,

and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.

2.

CHANNEL CALIBRATION ** at least once per 18 months.

b.

Performance of a CHANNEL FUNCTIONAL TEST:

1.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.

At least once per 31 days.

c.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 3.0 cps *** with the detector fully inserted.#

"With IRM's on range 2 or below.

• • Neutron detectors may be excluded from CHANNEL CALIBRATION.

• • • May be reduced, provided the source range monitor has an observed count rate and signal-to-noise ratio on or above the curve shown in Figure 3.3 6-1.

1. During initial startup test program, SRM detectors may be partially withdrawn prior to IRM on scale indication provided that the SRM channels j

remain on scale above 100 cps and respond to changes in the neutron flux.

j i

l LIMERICK - UNIT 2 3/4 3-88 Amendmen t No. 3

f9 REFUELING OPERATIONS

- 3/4.9.2' INSTRUMENTATION--

LIMITING CONDITION FOR OPERATION 3.9.2 At least two source range mon'itor-(SRM) channels" shall be OPERABLE' and inserted to-the-normal' operating level with:

Continuous visual indication in the control room, a.

b.

At least one with audible-alarm in the control room, i

One of the required SRM detectors located in the quadrant where CORE c.

ALTERATIONS are being performed and the other required SRM_ detector located in an adjacent quadrant, and I

L d.

Unless adequate SHUTDOWN MARGIN'has been demonstrated, the " shorting links" shall be removed from the RPS circuitry prior to and dtiring i

the time-any control rod is withdrawn.**

APPLICABILITY:

OPERATIONAL CONDITION S.***

ACTION:

With the requirements'of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS;and insert all insertable

}

control rods.

SURVEILLANCE REQUIREMENTS i

4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:

j a.

At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:

1.

Performance of a CHANNEL CHECK,-

a 2.

Verifying the detectors are inserted to the normal operating level, and 3.

During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE 1

ALTERATIONS are being performed and another is located in an

.t

. adjacent quadrant.

i l

• These channels are not required when sixteen or fewer fuel assemblies, ad-jacent to the SRMs, are in the core.

The_use of special movable detectors-i q

during CORE ALTERATIONS in place of the normal SRM nuclear detectors-is per-missible as long as'these special detectors are connected to the normal SRM circuits.

• • Not required for control rods removed per Specification'3.9.10.1 or 3.9.10.2.

I

~

• • • See Special Test Exception, Specification 3/4.10.7.

LIMERICK - UNIT 2 3/4 9-3

1

.I REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) b.

Performance of a CHANNEL FUNCTIONAL TEST:

i 1.

.Within'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 1

2.

At least once per 7 days.

i i

c.

-Verifying that the channel count rate is at least 3.0 cps:*

4 1.-

Prior to control rod withdrawal, 2.

Prior.to 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 /> during CORE ALTERATIONS, and 3.

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

t d.

Verifying, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to 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 />.

during,.that the'RPS circuitry " shorting. links" have been removed-during:

l 1.

The time any control rod is withdrawn,** or s

\\

2.

Shutdown margin demonstrations.

l l

l l

4 r

• May be reduced, provided the source range monitor has an observed count rate and signal-to-noise ratio on or above the curve shown in Figure 3.3.6-1.

'l These channels are not required when sixteen or' fewer. fuel assemblies,-

adjacent to the SRMs, are in the core.

1

• • Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LIMERICK - UNIT 2 3/4 9-4 Amendment No. 3 m.

- m.

u

- m

• -m-d w

'