Text

Amend 47 to License NPF-62,revising Tech Specs to Remove Requirement for Isolation of Containment Monitoring & Process Sampling Sys Upon Containment Bldg Exhaust High Radiation Signal
	ML20028G953
Person / Time
Site:	Clinton
Issue date:	09/25/1990
From:	Hannon J; Office of Nuclear Reactor Regulation
To:	;
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ML20028G954	List: ML20028G953; ML20028G957; ML20028G958;
References
	NUDOCS 9010040256
	Download: ML20028G953 (15)
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..

((gho hayg'#g UNITED STATES l

NUCLEAR REGULATORY COMMtSSION E

WASHl890 YON, D, C,20666 r

ILLIN015 POWER COMPANY ET AL.

DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License No. NPF-62 1.

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

p A.

The application for amendment by 1111nois Power Company * (IP),

and Soyland Power Cooperative, Inc. (the licensees) dated February 5, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chanter I; B.

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

Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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; D.

The issuance of this amendment will not b'e inimical to the common defense and security or to the health and safety of the pub'ic; 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.

AccordinglyIndicatedintheattachmenttot11slicenseamendment,andthe license is am 2.

cations as paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:

' Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc.'and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

9010040256 900925 PDR ADOCK 05000461:

P PNV

(- 'c 2,

(2) Technj,{il Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environa. ental Protection Plan contained in Appendix B, as revised through Amendment No. 47

. are hereby incorporated into this license.

Illinois Power Company shall operate the facility in accordance with the Technical Specifications-and the Environmental Protection Plan.

3.

This license a.andment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f/

+ ~ 72 ohn N. Hannon, Director Proiect Directorate 111-3 DivisionofReactorProjects-!!!,

IV, Y and Spec.ial Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 25, 1990 l

ATTACHMENT TO LICENSE AMENDMENT N0. 47 i

FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 i

Replace the following pages of the Appendix "A" Technical Specifications vith the attached riges.

The revised pages are identified by amendment number and j

contain vertical lines indicating the area of change. Corresponding overle0f pages are provided to maintain document completeness.

Remove Insert 3/4 3-13 3/4 3-13 t

3/4 3-20 3/4 3-20 3/4 3-25 3/4 3-25 3/4 3-27 3/4 3-27 3/4 6-36 3/4 6-36 3/4 6-39 3/4 6-39 3/4 6-40 3/4 6-40 i

r r

^

p TABLE 3.3.2-1 k

CRVICS INSTRUMENTATION E

^

MINIMUM OPERABLE APPLICABLE g

ISOLATION CHANNELS PER TRIP OPERATIONAL q

TRIP FUNCTION SIGNAL tt SYSTEM CONDITION ACTION 1.

PRIMARY AND SECONDARY CONTAITHENT ISOLATION a.

Reactor Vessel Water Level-Low Low, B(b)(f) 2(a) 1, 2, 3 20 Level 2 25 2 *)

1, 2, 3 29 I

b.

Reactor Vessel Water Level-Low B

Low, level 2 (ECCS Div. I and II) c.

Reactor Vessel Water Level-Low B

2(a) 1, 2, 3 29 Low,' Level 2 (ECCS Div. III) d.

Drywell Pressure - High L(b)(f) 2 *)

1, 2, 3 20 I

e.

Drywell Pressure - High L

ga) 1, 2, 3 29 A

y (ECCS Div. I and II)

U f.

Drywell Pressure - High (ECCS L

2(a) 1, 2, 3 29 Div. III) g.

Containment Building Fuel Transfer Z(b)(f) 2 *)

25 I

Pool Ventilation Plenum Radiation - High h.

Containment Building Exhaust Radiation - High M(b)(f) 2(a) 1, 2, 3 29 25 i.

Containment Building Continuous 5(b)(f) 2(a) 1, 2, 3 29 Containment Purge (CCP) Exhaust 25 E

Radiation - High e

I) 5 j.

Reactor Vessel Water Level-Low U

2 I, 2, 3 29 Low Low, Level 1 25 k.

Containment Pressure-High' P

1(k)(1) 1, 2, 3 29 y

25.

0

l2 TABLE 3.3.2-1 (Continued)

"zg CRVICS INSTRUMENTATION z

c5 MININUM OPERABLE APPLICABLE ISOLATION CHANNELS PER TRIP OPERATIONAL

[

TRIP FUNCTION SIGNAL tt SYSTEM CONDITION ACTION 1.

Main Steam Line Radiation - High C

2(a) 1, 2, 3 23 m.

Fuel Building Exhaust (b)(f)(j) 2(a) 1, 2, 3 25 Radiation - High 25 n.

Manual Initiation R(b)(f) 1 1,2,3 26 25 APPLICABLE ISOLATION APPLICABLE OPERATIONAL 2.

MAIN STEAM LINE ISOLATION t SIGNAL TABLE NOTES CONDITIONS ACTION w

a.

Reactor Vessel Water Level-Low 0

Low Low, level 1 U

NA 1,2,3 20 i

b.

Main Steam Line Radiation - High C

d 1, 2, 3 23 c.

Main Steam Line Pressure - Low H

NA 1

23 d.

Main Steam Line Flow - High D

NA 1, 2, 3 23 e.

Condenser Vacuum - Low J

NA 1, 2**, 3**

23 f.

Main Steam Line Tunnel Temp.

- High E

NA 1, 2, 3 23 g.

Main Steam Line Tunnel a Temp.

- High F

NA 1,2,3 23 h.

Main Steam Line Turbine 81dg.

Temp. - High G

p 1, 2, 3 23 l

p i.

Manual Initiation R

NA 1, 2, 3 22

s

=

t+

e 4.

e -

w.

m

=.

.m-.

_ _.. _ _ _,___._____________-_m_____._.__.m_._mm

TABLE 3.3.2-1 (Continued)

CRVICS INSTRUMENTATION ACTION ACTION 20 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 21 Deleted.

ACTION 22 With one channel in either trip system inoperable restore the manual initiation function to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTIO!

'5 CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling irradiated fuel in the primary or secondary containment may continue provided that SECONDARY 3

CONTAINMENT INTEGRITY is established with the standby gas treatment system operating within I hour.

ACTION 26 Restore the manual initiation function to OPERABLE stat'us within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 27 Close the affected system isolation valves within I hour and l

declare the affected system inoperable.

ACTION 28 Lock the affected system isolation valves closed within I hour l

and declare the affected system inoperable.

ACTION 29 Operations may continue provided that the affected CRVICS isola-tion valve (s) are closed within I hour and, as appropriate, declare the affected system or component inoperable and follow any ACTIONS appropriate to Specifications of the affected system.

Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i i

CLINTON - UNIT 1 3/4 3-19 1

d

7 TABLE 3.3.2-2 c,

C 25 CRVICS INSTRUMENTATION SETPOINTS e

h TRIP FUNCTION TRIP SETPOINT-ALLOWABLE VALUE h

1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

Low Low, Level 2 2 -45.5 in.*

1 -47.7 in.

b.

Reactor Vessel Water Level - Low Low, level 2 (ECCS Div. I ared II) 3 -45.5 in.*

2 -47.7 in.

c.

Reactor Vessel Water Level - Low Low, Level 2 (ECCS Div. III) 2 -45.5 in.*

2 -47.7 in.

d.

Drywell Pressure - High 1 1.68 psig i 1.88 psig 1

e.

Drywell Pressure - High g,

(ECCS Div. I and II) i 1.6F psig i 1.88 psig o

f.

Drywell Pressure - High (ECCS Div.III)

$ 1.68 psig i 1.88 psig g.

Containment Building fuel Transfer Pool Ventilation Plenum Radiation - High 5 100 mR/hr i 500 mR/hr h.

Containment Building Exhaust Radiation - High i 100 mR/hr

$ 400 mR/hr p

i.

Containment Building Continuous g

Containment Purge (CCP) Exhaust g

Radiation - High 1 100 mR/hr 5 400 mR/hr e

5 j.

Reactor Vessel Water Level Low-g Low Low-Level 1 3-145.5 in.*

3-147.7 in.

~

f:

~

l e

h

1

\\

'l

]

TABLE 3.3.2-3 CRVICS INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds) 1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION 3.

Reactor Vessel Water Level - Low Low, Level 2 NA i

b.

Reactor Vessel Water Level - Low Low, Level 2 t

(ECCS Div. I and II)

NA c.

Reactor Vessel Water Level - Lov Low, level 2 i

(ECCS Div. III)

NA d.

Drywell Pressure - High NA i

i e.

Drywell Pressure - High (ECCS Div. I and II)

NA f.

Drywell Pressure - High (ECCS Div. III)

NA g.

Containment Building Fuel Transfer Pool Ventilation Plenum Radiation - High NA h.

Containment Building Exhaust Radiation - High NA l

1.

Containment Building Continuous Containment Purge (CCP) Exhaust Radiation - High NA j.

Reactor Vessel Water Level-Low Low Low, Level 1 NA k.

Containment Pressure - High NA 1.

Main Steam Line Radiation - High NA m.

Fuel Building Exhaust Radiation - High NA n.

Manual Initiation NA 2.

MAIN STEAM LINE ISOLATION a.

Reactor Vessel Water Level - Low Low Low, Level 1

< 1.0*

b.

Main Steam Line Radiation - High NA c.

Main Steam Line Pressure - Low

< 1.0*

d.

Main Steam Line Flow - High 7 0.5*

e.

Condenser Vacuum - Low RA f.

Main Steam Line Tunnel Temp. - High NA g.

Main Steam Line Tunnel A Temp. - High NA h.

Main Steam Line Turbine Bldg. Temp. - High NA 1.

Manual Initiation NA 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High NA b.

A Flow Timer NA c.

Equipment Area Temp. - High NA d.

Equipment Area A Temp. - High NA e.

Reactor Vessel Water Level - Low Low, Level 2 NA f.

Main Steam Line Tunnel Ambient Temp. - High NA CLINTON - UNIT 1 3/4 3-25 Amendment No. 47 m

4 l

TABLE 3.3.2-3 (Continued) l CRVICS INSTRUMENTATION RESPONSE TIME i

i TRIP FUNCTION RESPONSE TIME (Seconds) 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION (Continued) i g.

Main Steam Line Tunnel a Temp. - High NA h.

SLCS Initiation NA i.

Manual Initiation NA 4.

REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION a.

RCIC Steam Line Flow - High NA b.

RCIC Steam Line Flow High - Timer NA c.

RCIC Steam Supply Pressure - Low NA d.

RCIC Turbine Exhaust Diaphragm Pressure - High NA i

e.

RCIC Equipment Room Ambient Temp. - High NA f.

RCIC Equipment Room a Temp. - High NA g.

Main Steam Line Tunnel Ambient Temp. - High NA h.

Main Steam Line Tunnel a Temp. - High NA i.

Main Steam Line Tunnel Temp. Timer NA j.

Drywell Pressure - High NA

k. 'Hanual Initiation NA 1.

RHR/RCIC Steam Line Flow - High NA m.

RHR Heat Exchanger Rooms A, B Ambient Temp. - High NA n.

RHR Heat Exchanger Rooms A, B a Temp. -

High NA 5.

RHR SYSTEM ISOLATION a.

RHR Heat Exchanger Rooms A, B Ambient Temp.

- High NA b.

RHR Heat Exchanger Rooms A, 8 A Temp.

- High NA c.

Reactor Vessel Water Level - Low, Level 3 NA d.

Reactor Vessel Water Level - Low Low Low, Level 1 NA 4

e.

Reactor Vessel (RHR Cut-in Permissive)

Pressure - High NA f.

Drywell Pressure - High NA g.

Manual Initiation NA

CRVICS instrumentation response time for MSIVs only.

No diesel generator delays assumed.

L CLINTON - UNIT.1 3/4 3-26

TABLE 4.3.2.1-1 r-k CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'E e

c CHANNEL OPERATIONAL 5

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH d

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED w

1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

Low Low, level 2 5

M R(b) 1, 2, 3, #

b.

Reactor Vessel Water Level -

Low Low, Level 2 (ECCS ID)

Div. I and II) 5 M

R 1, 2, 3 c.

Reactor Vessel Water Level -

Low Low, Level 2 (ECCS Div. III)

S M

R(b) 1, 2, 3 m1 d.

Drywell Pressure - High 5

M R(b) 1, 2, 3

[

e.

Drywell Pressure - High (ECCS Div. I and II)

S M

R(b) 1, 2, 3 N

f.

Drywell Pressure - High b)

(ECCS Div. III)

S M

R 1, 2, 3 g.

Containment Building Fuel Transfer Pool Ventilation Plenum Radiation - High 5

M R

h.

Containment Building Exhaust Radiation - High 5

M R

1, 2, 3, #

,l i.

Containment Building Contin-g' uous Containment Purge j

(CCP) Exhaust Radiation -

High S

M R

1, 2, 3, #

e 5

O

?

TABLE 4.3.2.1-1 (Continued)

CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS h

CHANNEL OPERATIONAL e

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c-TRIP FUNCTION CHECK TEST -

CALIBRATION SURVEILLANCE REQUIRED 5

1.

PRIMARY AMO SECONDARY CONTAINMENT ISOLATION (Continued) v j.

Reactor Vessel Water Level-Low Low Low, Level 1 5

M R(b) 1,2,3,#

k.

Containment Pressure - High 5

M R

1, 2, 3, #

1.

Main Steam Line Radiation -

High 5

M R

1,2,3 m.

Fuel Building Exhaust Radiation - High S

M R

1,2,3,#

w n.

Manual Initiation MA R

NA 1,2,3,#

1 w

2.

MAIM STEAM LINE ISOLATION a$

a.

Reactor Vessel Water Level -

Low Low Low, Level 1 S

M R(b) 1,2,3 b.

Main Steam Line Radiation -

High 5

M R

1, 2, 3 c.

Main Steam Line Pressure -

Low S

M R(b) y d.

Main Steam Line Flow - High 5

M R(b) 1, 2, 3 e.

Condenser Vacuum - Low S

M R(b) 1, 2**, 3**

f.

Main Steam Line Tunnel Temp. - High 5

M R

1, 2, 3 g.

Main Steam Line Tunnel a Temp. - High 5

M R

1, 2, 3 h.

Main Steam Line Turbine Bldg.

Temp. - High 5

M R

1, 2, 3 i.

Manual Initiation MA R

NA 1,2,3 e

_m,.. _..... _ _..

TABLE 3.6.4-1 (Continued)

~

p CONTAINMENT ISOLATION VALVES E

U z

MAXIMUM SECONDARY c

VALVE APPLICABLE ISOLATION CONTAINMENT TEST PENETRATION ISOLATION OPERATIONAL TIME BYPASS PATH PRESSURE g

MUMBER NUMBER SIGNAlt_

CONDITIONS

[ Seconds) _(YES/MO)

(psin)*

Automatic Isolation Valves (Continued)

28) Instrument Air Supply 57 IIA 005 1, 2, 3,#

Yes 9.0 IIA 006 U

20 U

20

29) Instrumert Air Bottles 58 IIA 0128 1, 2, 3,#

Yes 9.0 L, B, R 19

30) Service Air Supply 59 R

ISA030 1, 2, 3,#

Yes 9.0 1SA029 8, L, R 16 T

B, L, R 16 g 31) RWCU Suction Line 60 i

1G33-F001 1, 2, 5**

No 9.0 B,F,N,1,2,E, 20 IG33-F004 X, R B,F,N,1,2.E, 20 4

1 X, R

32) RWCU Return to Filter 61 1

1G33-F053 1,2,3 No 9.0 l

B, F, N, 1, 2, E, 21 j

1G33-F054 X, R i

B, F, N, 1, 2. E, 21 X, R

33) Hydrogen Recombiner Supply 62 1HG008 1, 2, 3,#

Yes 9.0 B, L, R

34) RWCU To RHR/FW 117 64 1G33-F040 1, 2, 3 No 9.0 8, F, N, 1, 2, E, 21 1G33-F039 X, R B, F, N, 1, 2, E, 21 X,' R i.

TABLE 3.6.4-1 (Continued) b CONTAINMENT ISOLATION VALVES 5

E e

MAXIMUM SECONDARY c

APPLICABLE ISOLATION CONTAINMENT TEST 5

VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS PATH PRESSURE

]

NUMBER NUMBER SIGNAlt CONDITIONS (Seconds)

(YES/NO)

(psig)*

Automatic Isolation Valves (Continued)

35) RWCU Transfer To Radwaste 65 1, 2, 3,#

Yes 9.0 IWX019 B, L, R 2

1WX020 B, L, R 2

36) Process Sampling 68 1, 2, 3,#

NA Yes 9.0 1P5016 B,L,R IPS017 B,L,R w1 IP5022 8, L, R IP5023 B,L,R e

d, IP5034 B,L,R IP5035 B, L, R IPS055

8. L, R IPS056 B, L, R IPS069 B,L,R IPS070 8, L, R

37) DW/ Cont.. Equip. Drair.

69 1,2,3 No 9.0 1RE021 B,L,R 16 1RE022 B,L,R 16

38) DW/ Cont. Floor Drain 70 1, 2, 3 No 9.0 y

1RF021 B, L, R 16 s

1RF022 B, L, R 16 e

g

39) Hydrogen Recombiner Supply 71 1, 2, 3,#

Yes 9.0 1HG001 8, L, R 117

?

~

40) Hydrogen Recombiner Return 72 1, 2, 3,#

Yes 9.0 0

1HG004 B, L, R 117 O

8 u

TABLE 3.6.4-1 (Continued) n C-CONTAINMENT ISOLATION VALVES 5g MAXIMUM SECONDARY APPLICABLE ISOLATION CONTAINMENT TEST VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS PATH PRESSURE c5 NUMBER NUMBER SIGNAlt CONDITIONS (Seconds)

(YES/NO) fpsig)*

-4 Automatic Isolation Valves (Continued)

55) DW Chilled Water Supply 109 1, 2, 3 No 9.0 IVP004A L, U 74 IVP005A L, U 74

56) DW Chilled Water Return 110 1, 2, 3 No 9.0 IVP014A L, U 74 IVP015A L, U 74

57) Cont. Bldg. HVAC 113 1, 2, 3,#

Yes 9.0 IVR006A B, i., M, Z, 5, R 6

4 IVR0068 B,L,M,Z,5,R 6

e

58) Cont. Monit.

153 1,2,3 NA No

. 9. 0 ICM022 B, L, R ICM023 B

L, R ICM025 B, L, R ICM026 B. L, R

59) Hydrogen Recombiner Supply 166 1, 2, 3,#

Yes 9.0 1HG005 B, L, R 117

60) Containment HVAC 169 1,2,3 NA No 9.0 g

IVR035 B,L,M,Z,5,R g

IVR036 B,L,M,Z,5,R g-IVR040 B,L,M,Z,5,R g

IVR041 B,L,M,Z,5,R c+

r

61) Cont. Monit.

173 1,2,3 NA No 9.0 o

ICM048 B, L. R O-ICM047 B,L R ICM011 B, L, R ICM012 B, L, R

TABLE 3.6.4-1 (Continued) b CONTAINMENT ISOLATION VALVES E

MAXIMUM SECONDARY c

APPLICABLE ISOLATION CONTAIMMENT TEST 5

VALVE PENETRATION ISOLATION

. OPERATIONAL TIME BYPASS PATH PRESSURE H

NUMBER NUMBER SIGNAlt CONDITIONS (Seconds)

(YES/MO)

(psig)*

Automatic Isolation Valves (Continued)

62) Instrument Air Bottles 206 1, 2, 3,#

Yes 9.0 11A0138 L, B, R 19

63) Process Sampling 210 1, 2, 3,#

NA Yes 9.0 1P5038 B,L,R IP5037 B,L,R IPSO 48 B,L,R m}

IPSO 47 B,L,R IPS004 B, L, R 4

IPS005 8, L, R o

IPS010 B,L,R IPS009 B,L,R IP5031 B,L,R IP5032 B,L R E

e O

---

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