Text

Amend 41 to License NPF-58,specifying Exceptions to TS 4.0.4 for IRMs & SRMs When Performing Plant Shutdowns from Operational Condition 1
	ML20091A790
Person / Time
Site:	Perry
Issue date:	03/20/1992
From:	Hall J; Office of Nuclear Reactor Regulation
To:	;
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ML20091A801	List: ML20091A790; ML20091A803;
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	NUDOCS 9203300174
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UNITED STATES E

NUCLEAR REGULATORY COMMISSION g,c,<

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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.

DOCKET N U p-440 PERRY NVCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING llCENSE Amendment No. 41 License No. NPF-58 1.

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

A.

The application for amendment by The Cleveland Electric illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power (,ompany, and Toledo Edison Company (the licensee >) dated March 28, 1991, 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 (1) that the activities authorized by this amendment can be conducted without endan;ering the healt:,

safety of the publ ic, and (ii) that such activities - will be conducted in compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendr ent, and paragrap:. 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:

9203300174 920320 PDR ADOCK 05000440 p

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. (2) ledtrLigl Specific 311pp,1 The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 41 are hereby incorporated into this license.

The Cleveland Electric 111uminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

1 FOR THE NUCLEAR REGULATORY COMMISSION b li k.

.es R. Hall, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation d

Attachment:

Changes to the Technical Specifications Date of issuance: Shrch 20,1992

m 4

AIJACHMENT TO LICENSE AMENDMENT NO. 41 FAtiLITY OPERATING LICENSE NO. NPF-58 DQ KET N0._50-440 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 are provided to maintain document completeness.

Remove Insert 3/4 3-1 3/4 3-1 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-55 3/4 3-55 3/4 3-59 3/4 3-59 3/4 3-81 3/4 3-81 l

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3/4.3 INSTRUMENTATION 3/ 4. 3.1 RE'iTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a mi imum, the reactor protection system !nstrumentation channels shown in Tabic

.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABillTY: As shown in Table 3.3.1-1.

l ACTION:

a.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and j

take the ACTION required by Table 3.3.1-1.

S T. " '

"'CE REQUIREMENTS P

4 L '.1 Each reactor protection system instrumentation channel shall be ce 1 s ated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TES. and CHANNEL CAllBRATION operations for the OPERAT10 MAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1, 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated auttmatic operation of all channels shall be performed at least once per 18 months.

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 N is the total number of redundant channels in a specific reactor trip system.

k 4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the CHANNEL FUNCTIONAL TEST and OMNNEL CALIBRATION surveillances for the Intermediate Range Monitors for entry 1,40 their applicable OPERATIONAL CONDITIONS (as shown in Table 4.3.1.1-1) from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after such entry.

An inoperable channel need not bEplaced in the tripped condition where this woald cause the Trip Function to occur.

In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

- The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur.

When a trip system can be placed ia the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip systt.. in the tripped condition.

PERRY - UNIT 1 3/4 3-1 Amendment No. 41 n

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i TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIMUM OPERATIONAL OPERABLE CHANNELS E.

FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)

ACTION

.i

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.' Intermediate Range Monitors:

r a.

Neutron Flux - High 2

3 1

3(bj 3

2 5

3 3

b.

Inoperative 2

3 1

3, 4 3

2 5

3 3

2.

Average Power Range Monitor (c);

a.

Neutron Flux.- High, Setdown 2

3 1

3(y1 3

2 ea1 5

3 3

Y b.

Flow Siased Simulated Thermal Power -'High-1 3

4 c.

Neutron Flux - High 1

3 4

d.

Inoperative 1, 2

-3 1

3 3

2 5

3 3

3.

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

4.

' Reactor Vessel Water Level - Low,-

Level 3 1, 2 2

1 5.

' Reactor Vessel' Water Level - High, 1,)

2 4

g

-Level 8 6.

Main Steam Line Isolation Valve -

i ')

4 4

f C1csure 7.

Main Steam Line Radiation -

Id)

High 1, 2 2

5 II) 8.

Drywell Pressure - High 1, 2 2

1

m TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS e

CHANNEL OPERATIONAL e

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

{

FUNCTIONAt_ UN7T CHECK TEST CALIBRATION (a)

SURVEILLANCE REQUIRED 1.

Intermadiate Range Monitors:

a.

Neutron Flux - High S/U.S,(b)

W R

2 l

5 W

R 3,4,5 b.

Inoperative NA W

NA 2,3,4,5 2.

Average Power Range Monitor:(f) i a.

Neutron Flux - High, S/U,5,(b)

W SA 2

l Setdown S

W SA 3, 5 b.

Flow Biaced Simulated l

Ih)

I Thermal Power - High 5,D W

W(d)(e)34(m), R ')

1 c.

Neutron Flux - High S

W W(d). SA 1

Y d.

Inoperative NA W

NA 1, 2, 3, 5 4

3.

Reactor Vessel Steam Dome I9) 1,2(3)'

Pressure - High S

M R

4.

Reactor Vessel Water Level -

I9}

Low, level 3 5

M R

1, 2 5.

Reactor Vessel Water Level -

I9)

High, Level 8 S

M R

1 6.

Main Steam Line Iso b tion g

Valve - Closure NA M

R 1

7.

Main Steam Line Radiation -

II) 3 High S

M R

1, 2 IU) fII 8.

Drywell Pressure - High S

M R

1, 2 P

9.

Scram Discharge Volume Water S

Level - High I9) 1, 2, 5(k) a.

Level Transmitter S

M R

I) b.

Float Switches NA M

R 1, 2, S

1 TABLE 4.3.1.1-1 (Continued)

E REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREPfENTS E

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH E

FUNCTIONAL UNIT CHECK TEST CALIB'MTION SURVEILLANCE REQUIRED U

10.

Turbine Stop Valve - Closure NA M

R 1

r

11. Turbine Control Valve fast Closure Valve Trip System Oil Pressure - Low NA M

R 1

12.

Reactor Mode Switch Shutdown Position NA R

NA 1,2.3,4,5

13. Manual Scram NA M

NA 1,2,3,4,5 Neutron detectors may be excluded from CHANNEL CALIBRATION.

j (a)

The IRM and SRM channels shall be determined to overlap for at least 1/2 decades dur. sg each startup (b) after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at lear >t 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.

R (c) Deleted

~

consist of the adjustment of the APRM channel to conform to the power values This calibration shal:

sf (d) calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL co POWER. Adjust the APRM channel if the absolute difference is greater than 2% c7 RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed w* thin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter reaching 25% of IATED THERMAL POWER.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.

(g) Calibrate trip unit setpoint at least once per 31 days.

p (h) Verify measured core flow (total core flow) to be greater than or equal to established core flow at the existing loop flow (APRM % flow).

<o E.

(i) This calibration shall consist of wrifying the 610.6 second simulated thermal power time constant.

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l P.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(k) With any control rod withdrawn.

Not applicable to control rods removed per 2

?

Specification 3.9.10.1 or 3.9.10.2.

3 (1) This function is not required to be OPERABLE when Drywell Integrity is not required.

(m) The CHANNEL CALIBRATION shall exclude the flow reference transmitters, these transmitters shall be calibrated at least once per 18 months.

_ _ _ _ _... _ _ _ ~ _ _ _ _. _

INSTRUMENTAi40N 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPFP.ATION 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:

With a control rod block instrumentation channel trip setpoint less a.

conservative than the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent 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.

SURVEILLANCE REQUIREMiNTS 4.3.6.1-Each of the above required control rod block trip systems and instrumentation channels shall be demonstrated OPERABLE by the performance of l

the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL LONDITIONS and at the frequencies shown in Table 4.3.6-1.

4.3.6.2 The provisions of Specification 4.0.4 are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION surveillances for the Intermed-iate Range Monitors and Source Range Monitors for entry into their applicable OPERATIONAL CONDITIONS (as shown in Table 4.3.6-1) from OPERATIONAL CONDITION 1 provided the surveillances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after such entry.

PERRY - UNIT 1 3/4 3-55 Amendment No. 41

)

e TABLE 3.3.6-1 A

CONTROL ROD BLOCK INSTRUMENTATION w

flE MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION

. gq 1.'

R00 PATTERN CONTROL SYSTEM a.

Low Power Setpoint 2

1, 2 60 l

b.

RWL - High Power 2

1 60 l

Setpoint l

2.

APRM a.

Flow Blased Neutron Flux -

Upscale 6

1 61 b.

Inoperative 6

1, 2, 5 61 c.

Downscale 6

1 61 d.

Neutron ? lux - Upscale, Startup 6

2, 5 61 3.

SOURCE RANGE MONITORS mA Detector not full in(a) 3 2#

61 a.

l y

2**

5 61 I

3 2#

61 b.

Upscale (b) 2**

5 61

-Inoperative (b) 3 2#

61 c.

2**

5 61 IC) f d.

Downscale 4.

INTERMEDIATE RANGE MONITORS l

a.

Detector not full in 6

2, 5 El l

b.

Upscale.

6 2, 5 61 c.

Inoperative 6

2, 5 61 d.

Downscale(d) 6 2, 5 61 5.

SCRAM OISCHARGE VOLUME i

a.

Water Level-High 2

1, 2, 5*

62 4

6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale 6

1 62 7.

REACTOR MODE SWITCH SHUTDOWN POSITION 2

3, 4 63

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l TABLE 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SUR'IEILLANCE REQUIREMENTS ret mQ CHANNEL OPERATIONAL i

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION (,'3 E

1.

ROD PATTERN CONTROL SYSTEM SURVEILLANCE REQUIRED X

t y

a.

Low Power Setpoint NA S/U(b) g 3g#

1, 2 b.

RWL - High Power Setpoint NA S/U(b) g i

gg y

2.

APRM Flow Biased Neutron Flux - Upscale a.

1) Flow Biased NA S/U(D),Wb) y 34(c)

2) High Flow Clamped NA y

I SA(c)

S/U b.

Incperative NA S/U

,W NA 1,2,5 y

c.

Downscale NA S/U W

SA 1

f d.

Neutron Flux - Upscale, Sta-tup NA S/UID),W SA 2, 5 g

3.

5085(CE RANGE MONITORS t

Y a.

Detector not full in NA S/U(b) W(dI NA 2**

5 i

b.

Upscale NA S/U

,W R

2**

5 i

c.

Inoperative NA S/U,.

W NA 2**

5 d.

Downscale NA S/U*),WId)

R 2**

5 4.

INTERMEDIATE RANGE MONITORS g

{

a.

Detector not full in NA S/U

,W NA 2, 5 g-b.

Upscale NA S/U(b),W(d)

R 2, S

(

a c.

Inoperative NA S/U NA 2, 5 i

S S/U(b)'W(d) d.

Downscale NA

,W R

)

f 5.

SCRAM DISCHARGE VOLUME 2, 5 i

g a.

Water Level - High NA M

R 1, 2, 5*

L 6.

REACTOR COOLANT SYSTEH RECIRCULATION FLOW

~

a.

Upscale NA S/U(b) g 34(c) 7 7.

REACTOR MODE SWITCH SHUTDOWN

)

{

POSITION l

NA R

NA 3, 4 i

l l

~

l TABLE 4.3.6-1 (Continued)

CONTROL R0D BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:

~

a.

Neutron detectors may be excluded from CHANNEL CALIRRATION.

b.

Within 7 days prior to startup.

c.

The CHANNEL CALIBRATION shall exclude the flow reference transmitters, these transmitters shall be calibrated at least once per 18 months.

d.

Trip setpoints are verified during weekly CHANNEL FUNCTIONAL TESTS.

"With more than cna control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- With IRMs on ringe 2 or below.

Calibrate trip unit setpoint at least once per 31 days.

i l

l l

PERRY - UNIT 1 3/4 3-60 Amendment No. 31

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_ 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 3 source range moni~ tor channels 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 con-trol rods to be fully inserted in the core and lock the reacto.' mode switch in the Shutdown position within one hour, j

SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above reauired 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 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 7 days prior to moving the reactor mode switch from the Shutdown position, and 2.

At least once per 31 days #

l c.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps *** with the detector fully inserted.

With IRM's on range 2 or below.

- Neutron detectors may be excluded from CHANNEL CALIBRATION.

- - Provided the signal-to-noise ratio is > 2.

The provisions of Specification 4.0.4 are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION surveillances for the Source Range Monitors for entry-into their applicable OPERATIONAL CONDITIONS (OPERATIONAL CONDITION 2*,- 3 and 4) from OPERATIONAL CCNDITION 1.'provided the surveil-lances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after such entry.

PERRY - UNIT 1 3/4 3-81 Amendment No. 41

i 4

_ INSTRUMENTATION TR.AYERSING IN CORE PROBE SYSTEM

~

LIMITING CONDITION FOR OPERAf!ON j

1 I

3.3.7.7 The traversing in-core probe systen shall be OPERABLE with either:

t Five movable detectors, drives and readout equipment to map the core, i

a.

{

i and indexing equipment to allow all five detectors to be calibrated in a common location.

OR i

b.

i With one or more TIP measurement locations inoperable, data may be replaced by data obtained from that location's symmetric counterpart 1

if the substitute TIP data was obtained from an OPERABLE measur i

location; provided the reactor core is operating in a type A control t

rod pattern and the total core TIP uncertainty for the present cycle has been determined to be less than 8.7 percent-(standard deviation).

Symmetric counterpart da;4 may be substituted for a maximum of ten TIP measurement locations.

APPLICABILITY: When the traversing in core probe is used for:

a.*

Recalibration of the LPRM detectors. and b.*

Monitoring the APLHGR, LHGR, MCPR, or NFLPD.

ACTION:

With the traversing in-core prore system inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specification-3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS-t i

4.3.7.7 normalizing each of-the above required detector outputs j

to Ose when required for the LPRM calibration function.

0nly the detector (s) in the location (s) of interest are required to be OF.RABLE PERRY - UNIT 1 3/4-3-82 Amendment No. 25.30 l

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ML20091A790

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