ML20141N118

From kanterella
Jump to navigation Jump to search
Amends 115 & 98 to Licenses DPR-53 & DPR-69,respectively, Revising Tech Specs to Allow Use of 4-inch post-accident Hydrogen Purge Line for Containment Purge During Normal Operation
ML20141N118
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/20/1986
From: Thadani A
Office of Nuclear Reactor Regulation
To:
Baltimore Gas & Electric Co (BGE)
Shared Package
ML20141N119 List:
References
DPR-53-A-115, DPR-69-A-098 NUDOCS 8603030601
Download: ML20141N118 (17)
v • d • e


Text

_.

8

! s Reg 6 %

UNITEJ 8TATES

[

NUCLEAR REGULATORY COMMISSION l

m w ee.orow,p.c.aseen s

's.,...../

BALTIMORE GAS AND ELECTRIC COMPANY C0CKET NO. 50-317 CALVEPT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. DPR-53 1.

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

A.

The applications for amendment by Baltimore Gas a Electric Company (thelicensee)datedDecember 22, 1933 and March 26, 1984 as supplemented by letters dated March 21, 1985 and August 9, 1985, comply 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 Chapter I; B.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Corsnission t C.

There is reasonable assurance (1) that the activities authorized by this ametidment 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 comon 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.

8603030601 860220 DR ADOCK 05000317 p

PDR

i 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. DPR-53 is hereby amended to reed as follows:

(2) Technical Specifications The Tech.9fcal Specifications contained in Appendix A as i

revised through Amendaunt No.115, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION I

A hok C. Thadant. Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of issuance:

February 20, 1986 t

i 1

I f

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

i l.

I j

ATTACHMENT TO LICENSE AMENDMENT NO.115 l

I FACILTIY OPERATING LICENSE NO. OPR-53 i

DOCKET NO. 50-317 I

i Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating tlw areas of change.

The correspending overleaf pages are provided to maintain doc eent completeness.

i Remove Pa2es Insert Pages I

a 1

3/4 6-9e 3/4 6-9e 3/4 6-23 3/4 6-23 3/4 6-25 3/4 6-25

~

~

}.'

i J

l i

1 l

i t

\\

l 4

1 i

i I

r r

I i

i

}

1

. -. -. ~

_., _.. _ _ _ _, _...., _ _.. _., -. _,.., -. _ - -.. _,. _ _ _ _ _. - - _,. -.., _ _, - -... - _ -. ~....,,.

CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEM LIMITING CONDITION FOR OPERATIO?i 3.6.1.7 The containment purge supply and exhaust isolation valves shall be closed by isolating air to the air operator and maintain;ng the solenoid air l

supply valve deenergized.

\\

APPLICABILITY:

MODES 1, 2, 3 and 4 l

ACTION:

a.

With one containment purge supply and/or one exhaust isolation valve open, close the open valve (s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With one containment purge supply and/or one exhaust isolation valve inoperable due to high 1-dage, repair the valve (s) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

r i

i i

SURVE!LtANCE REQUIREttENTS I

4.6.1.7 The 48-inch containment purge supply and exhaust isolation valves shall s

be determined closed at least once per 31 days, by verifying that power to the solenoid valve is removed.

I i

i 6

i i

CALVERT CLIFFS - UNIT 1 3/4 6-94 knendment No./ /,/pp,g 9 i

i

CONTAINMENT SYSTEMS CONTAINMENT VENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The containment vent isolation valves MOV 6900 and MOV.6901 shall be maintained closed by tagging the motor power supply breakers open and main-taining the keyed hand switches locked in the closed position.*

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

With one or both containment vent isolation valves open, close the open valve (s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN wi_ thin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.8 The containment vent isolation valves shall be determined closed at 5 least once per 31 days by verifying that power to the motor operators is removed and the valves indicate shut. *

  • These requirements shall be deleted upon initial operability of the CRS isolation signal input to MOV 6900 and MOV 6901.

CALVERT CLIFFS - UNIT 1 3/4 6 9e Amendment No g 3, 115 l

t

1 E

TABLE 3.6-1 (Continued)

G CONTAINttENT ISOLATION VALVES 1

P PENETRATION ISOLATION ISOLATION VALVE ISOLATION 4

NO.

CHANNEL _

IDENTIFICATION NO.

FUNCTION TIME (SECONDS) t 44 E

FP-141-A Fire Protection NA c

NA FP-141-B NA l

{

NA FP-6200-MOV*

NA l

47A MA PS-6540A-SV*

Hydrogen Sample Outlet NA MA PS-6507A-SV*

NA

~

478 NA PS-6540E-SV*

Hydrogen Sample Outlet NA y

NA PS-6507E-SV*

MA T

U 47C NA PS-6540F-SV*

Hydrogen Sample Outlet NA l

NA PS-6507F-SV*

NA 1

470 NA PS-65406-SV*

Hydrogen Sampie Return

, MA NA PS-6507G-SV*

NA 5

48A SIAS-8 W-6900-MDV(4)

Contairunent Vent Isolation

< 15 y

SIAS-A HP-6901-MOV(4)

_ 15 E.

-?

5 DeW

TABLE 3.6-1 (Continued)

}

CONTAI MENT ISOLATION VALVES P

PENETRATION ISOLATION ISOLATION VALVE ISOLATION NO.

CHAINIEL IDENTIFICATION NO.

FUNCTION TIME (SECONDS)

- 488 NA HP-104 Hydrogen Purge Inlet NA g

NA HP-6903-MDV NA 3

494 m

PS-65408'-SV*

Hydrogen Sample NA NA PS-65078-SV*

NA 498 m

PS-6540C-SV*

Hydrogen Sample m

m PS-6507C-SV*

NA 49C NA PS-65400-SV*

Hydrogen Sample m

4, MA PS-65070-SV*

m 50 NA 311ad Flange ILRT

'm M

Blind Flange m

g 59 m

SFP-170 Refueling Pool Inlet m

m SFP-171 m

=

.&f.

50 m

ES-144 Steam to Reactor Head Laydown M

NA ES-142 NA E

k Gab O

e

l l

t TABLE 3.6-1 (Continued) h CONTAINMENT ISOLATION VALVES PENETRATION ISOLATION ISOLATION VALVE ISOLATION P

N0.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECOND3) 61 NA SFP-176 Refueling Pool Outlet NA NA SFP-174 NA NA SFP-172 NA e5 NA SFP-189 NA w

s 62 S'IAS A PH-6579-MOV Containment Heating Outlet

< 13 s

64 NA PH-376 Containment Heating Outlet NA R

=

?

lX (1) Manual or remote manual valve which is closed during plant operation.

(2) May be opened below 300*F to establish shutdown cooling flow.

(3) Containment purge valves will be shut in MODES 1, 2, 3, and 4 per TS 3/4 6.1.7.

l f

  • May be open on an intermittent basis under administrative control.-

o.

l 2

    • Containment purge isolation valves isolation times will only apply in MODE 6 when the valves are a

required to be OPERABLE and they are open.

Isolation time for containment purge isolation valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7, during which time these valves must remain closed.

(4) Containment vent isolation valves shall be opened for containment pressure control, airborne

=

{

radioactivity control, and surveillance testing purposes only.

,a sd

=

l z

G

CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

With one hydrogen analyzer inoperable, restore the inoperable analyzer i

to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With both hydrogen analyzers inoperable, restore at least one inoperable analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.5.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least bi-weekly on a STAGGERED TEST BASIS by drawing a sample from the waste gas system through the hydrogen analyzer.

4.6.5.2 Each hydrogen analyzer shall be demon:trated OPERABLE at least once i

per 92 days on a STAGGERED TEST BASIS by perfo. ring a CHANNEL CALIBRATION using sample gases in accordance with manufacturers' recommendations.

CALVERT CLIFFS - UNIT 1 3/4 6-26 Amendment No. $$,7/.E3.Jg3, 109

'o

~g UNITED STATES NUCLEAR REGULATORY COMMISSION n

s a

waswiwoTow. o. c. zosas

\\..... $

BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-69 1.

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

A.

The applications for amendment by Baltimore Gas & Electric Company (the licensee) dated December 22, 1983 and March 26, 1984 as supplemented by letters dated March 21, 1985 and August 9, 1985, comply 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 Chapter I; B.

The facility will operate in conformity with the applications, 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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.

l l

l l

(

  • 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. DPR-69 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION ok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 20, 1986 1

l I

i

ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.

Remove Pages Insert Pages 3/4 6-9b 3/4 6-9b 3/4 6-23

~

3/4 6-23 3/4 6-25 3/4 6-25

CONTAINMENT SYSTEMS CONTAINMENT VENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 ThecontainmentventisolationvalvesMOV6900andIbV6901shall be maintained closed by tagging the motor power supply breakers open and maintaining the keyed hand switches locked in the closed position.*

l APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or both containment vent isolation valves open, close the open.

valve (s) witoin one hour or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I SURVEILLANCE REQUIREMENTS 4

4.6.1.8 The containment vent isolation valves shall be detemined closed at least once per 31 days by verifying that power to the motor operators is removed and the valves indicate shut.*

  • These requirements shall be deleted upon initial operability of the CRS isolation signal input to MOV 6900 and MOV 6901.

CALVERT CLIFFS - UNIT 2 3/4 6-9b Amendment No./fy,98

-,,n,,,

,-,-r,,

.-nm,-.

h$

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES E2 PENETRATION ISOLATION ISOLATION VALVE ISOLATION NO.

CHANNEL IDENTIFICATION NO.

FUNCTION TIME (SECONOS) 44 NA FP-145-A Fire Protection NA gg NA FP-145-B NA

[j NA FP-6200-MOV*

NA m

47A NA PS-6540A-SV*

Hydrogen Sample Outlet NA NA PS-6507A-SV*

NA 478 NA PS-6540E-SV*

Hydrogen Sample Outlet NA NA PS-6507E-SV*

NA R

os 47C MA PS-6540F-SV*

Hydrogen Sample Outlet NA l

(;

NA PS-6507F-SV*

NA 47D NA PS-6540G-SV*

Hydrogen Sample Return MA NA PS-6507G-SV*

NA II 48A SIAS A HP-6900-MOV (4)

Containwent t ent Isolation

< 15 SIAS B HP-6901-MOV (4) 1 15 r+

E.

~N

4 52 TABLE 3.6-1 (Continued)

G gg CONTAINMENT ISOLATION VALVES F2 PENETRATION ISOLATION ISOLATION VALVE ISOLATION NO.

CHANNEL IDENTIFICATION NO.

FUNCTION a

TIME (SECOMOS) 488 NA HP-104 Hydrogen Purge Inlet NA c-NA HP-6903-MOV 25 NA

-e 49A NA PS-65408-Sy*

Hydrogen Sample NA NA PS-65078-SV*

NA d

498 NA PS-6540C-SV*

Hydrogen Sample NA NA PS-6507C-SV*

NA R

l 49C NA PS-65400-SV*

Hydrogen Sample NA A,

MA PS-65070-SV*

a NA 50 NA Blind Flange ILRT NA NA Blind Flange NA 59 NA SFP-178 Refueling Pool Inlet

![

NA NA SFP-179

=

NA Eb

+

k 60 NA ES-144 Steam to Reactor Head Laydown NA NA ES-142 me

?

NA 3=?

O t

9

_ TABLE 3.6-1 (Continued)*

CONTAINMENT ISOLATION VALVES

'I s E!

PENETRATION ISOLATION ISOLATION VALVE ISOLATION NO.

CHANNEL IDENTIFICATION NO.

FUNCTION

_ TIME (SECONOS)

'.S i

i P

'g 61 MA SFP-184 Refueling Pool Outlet t

?

NA SFP-182 NA e

NA SFP-180 NA i

c.

NA SFP-186 NA i

2 NA

\\

62 SIAS A PH-6579-MOV Containment Heating Outlet

_13 64 NA PH-387 Containment Her.n9 Inlet.

NA (1) Manual or remote manual valve which is closed during plant operation.

w1 (2) May be opened below 300*F to establish shutdown cooling flow.

4 I

L (3) Containment purge valves will be shut in MODES 1, 2, 3 and 4 per TS 3/4 6.1.7.

l

  • May be open on an intermittent basis under administrative control.

1 1

    • Containment purge isolation valves isolation times will only apply in MODE 6 when the valves are required to be OPERABLE and they are open.

Isolatie-time for containment purge isolation valves is NA for MODES 1, 2, 3 and 4 per TS 3/4 6.1.7, dur,3g which time these valves must remain closed.

I I

(4)

Containment vent isolation valves shall be opened for u ntainment pressure control, airborne j

{

radioactivity control, and surveillance testing purposes only.

I S

if h

i 4

I t

m'8 i

CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen analyzer inoperable, restore the inoperable analyzer

[

a.

to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With both hydrogen analyzers inoperable, restore at least one inoperable analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SlJRVEILLANCE REQUIREMENTS 4.6.5.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least biweekly on a STAGGERED TEST BASIS by drawing a sample from the Waste Gas i

System through the hydrogen analyzer indicator.

4.6.5.2 Each hydrogen analyzer shall be demonstrated OPERABLE at least l

once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRA-TION using sample gases in accordance with manufacturers' reconnendations.

l l

l l

CALVERT CLIFFS - UNIT 2 3/4 6-26 Amendment No. 52,55,55, 92 l

l

.v r,----_-2

,4.

e

-_

Retrieved from "https://kanterella.com/w/index.php?title=ML20141N118&oldid=4183210"