ML20071G130

Amends 128,122,148 & 144 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,revising TS 3/4.7.D by Adding Check Valves to Limiting Condition for Operational Statement of TS

ML20071G130
Person / Time
Site:	Dresden, Quad Cities
Issue date:	07/06/1994
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20071G134	List: ML20071G130 ML20071G167
References
NUDOCS 9407120060
Download: ML20071G130 (22)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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: 2 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCL(AR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 128 License No. DPR-19

'*. 'nclear Regulatory Commission (the Ct.imission) has found that:

The application for amendment by the Commonwealth Edison Company (the licensee) dated March 11, 1994, 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 1; The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; is reasonable assurance (i) that the activities authorized

,nerf of this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be condacted 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 amendment and paragraph 2.C,(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:

9407120060 940706 PDR ADOCK 05000237 P

PDR

i

, (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.128, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

N s license amendment is effective as of the date of its issuance; to ae implemented when the modifications are complete and prior to restart from any cold shutdown after June 30, 1994, or restart from the 14th af uel outage which ever is first.

FOR THE NUCLEAR REGULATORY COMMISSION ha. Cp Robert A. Capra Director Project Directorate 111-2 Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation

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ATTACHMENT 10 LICENSE AMLNDMENT NO. 12A FAtlLITY QPERATING LIC[RSE NO. DPR-19 DOCKET NO. 50-237 Revist-the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE JH51El 3/4.7-27 3/4.7-27 3/4.7-28 3/4.7-28 3/4.7-29 3/4.7-29

. ~ - -.. _ _ -.

F Dresden 11 DPR-19 Amendment No. 126 3.7 LISUlh CONDITION FOR 4.7 SURVEILLANCE RE0VIREMENTS a

gfir ll(>N (Cont'd.)

(Cont'd.)

d.

The fuel cask or irradiated fuel is not being moved in the reactor building.

)

2. If Srecification 3.7.C.1 cannot be met, restore Secondary Containment Integrity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be ir. at least Hot Shutdown w4 tnir the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> o a u. f.old Shutdown within

• * '011rwing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and c tali 3. the conditions

-' 1 (Decification

'e 3.' :.l.a through d.

D. Pr-y M ainnent D.

Primary Containment 1 s t' i' i r e al ve s isolation Valves

1. During reactor power 1.

The primary containment isolation

.:nt ticns, all valves surveillance shall be p r i c i. r, contairsent performed as follows:

isolation valves, all instru ent line excess flow a.

At least once per operating chett valves, and all cycle the operable primary referar.ce leg backfill containment isolation check valves shall be valves that are power operable except as operated and automatically i

specified in 3.7,0.2.

initiated shall be tested for simulated automatic initiation and closure times.

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3/4.7-27

e Dresden 11 DPR-19 Amendment No. 128 3.7 LIMITING CONDITION FOR 4.7 SURVElllANCE RE0VIREMENTS OPERA 1104 (Cont'd.)

(C or,t ' d)

b. At least once per operating cycle the instrument line flow check valves shall be tested for proper operation.

c. At least once per quarter:

(1)

All normally open power operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.

(2)

With the reactor power less than SOM of rated, trip main steam isolation valves (one at a time) and verify closure time.

d. At least twice per week the main steamline power-operated isolation valves shall be exercised by partial closure and subsequent reopening.

2. In tne event any primary 2.

Whenever a primary containment containment isolation valve isolation valve or any reference or any reference leg leg backfill check valve is I

oackfill check valve inoperable, the position of. at becomes inoperable, reactor least one other valve in each power operation may line having an inoperable valve continue provided at least shall be recorded daily, one valve in each line having an inoperable valve is in the mode corresponding to the isolation condition.

3/4.7-28 4

Dresden 11 DPR-19 Amendment No. 128 3.7 LIMITING CONDITION FOR 4.7 SURVEllLANCE REOUIREMENTS OPERA 110N (Cont'd.)

(Cont'd.)

3. If Specification 3.7,0.1

3. The temperature of the main and 3.7.D.2 cannot be met, steamline air pilot valves shall an orderly shutdown shall be recorded daily.

be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except for the Recirculation Loop Sample valves and the Drywell Air Sampling System i'x which can be rcepered af ter isolation for sampling.

4. The temperature of the main

4. When it is determined that the steamilne air pilot valves temperature of any main steamline shall be less than 170'F air,F, the main steamlinepilot valve is gre

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• os specified in 170 3.7.0 E below.

1 solation valves shall be demonstrated to be operable immediately and daily thereafter.

The demonstration of operability shall be according to Specification 4.7.D.l.d.

5. From and after the date that the temperature of any main steamline air pilot valve is found to be greater than 170*F, reactor operation is permissible only during the succeeding seven days unless the temperature of such valve is sooner reduced to less than 170'F, provided the main steamline isolation valves are operable.

3/4.7-29

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UhDTED SVATES t4UCLE AR REGULATORY COMMISSIOtJ

.%A5u 8. CM O '. LL.:M COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 122 License No. DPR-25

'i: clear Regulatory Commission (the Commission) has found that:

The application for amendment by the Commonwealth Edison company (the licensee) dated March 11, 1994, 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; The facility will operate in conformity with the application, the trovisions of the Act and the rules and regulations of the tommission; tere is reasonable assurance (i) that the activities authorized bj 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 Commissinn'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 tu the Technical Specifi-cations as indicated in the attachment to this license amendment and oaragraph 3.B. of facility Operating License No DPR-25 is hereby amended to read as follows:

.g.

T shnical SDecifications b.

i The Technical Specifications contained in Appendix A, as revised through Amendment No. 122, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

~

Tris license amendment is effective as of the date of its issuance; to S t-wplemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISS10ft

@Ja.c&

Robert A. Capra, Director Project Directorate 111-2 Division of Reactor Projects - 111/IV Office of fluclear Reactor Regulation the Technical 5:

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I ATTACHMEN1 TO LICENSE AMENDMENT NO. i??

FAClllTY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Revi>e the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3/4.7-27 3/4.7-27 3/4.7-28 3/4.7-28

Dresden 111 DPR-25 Amendment No. 122 3.'

.j!':T:tG CONDITION FOR 4.7 SMRVEILLANCE RE0VIREMENTS OPERATION (Cont'd.)

(Cont'd.)

c.

The fuel cask or irradiated fuel is not being moved in the reactor building.

2. If Specification 3.7,0.1 cannot be met, restore Secondary Containment Integrity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or t: ir at least Hot Shutdown a"rt the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> e,c Tn Cold Shutdown within

"+ ':llowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and estdri'sb the conditions

.tJ in Specification

' 7..!.a through d.

o r., tontain ent D. Primary Containment

solation Valves isolation Valves 4"n - a-+cr power

1. The primary containment isolation vpe.at r,

corditions, all valves surveillance shall be prirary containment performed as follows:

1 solation valves, all

'nstru ent line excess flow check valses, and all At least once per operating a.

reference leg backfill cycle the operable primary check valves shall be containment isolation cperable e> cept as valves that are power spe:ified in 3.7.D.2.

operated and automatically initiated shall be tested for simulated automatic initiation and closure

times, b.

At least once per operating cycle the instrument line flow check valves shall be tested for proper operation.

3/4.7-27 l

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Dresden 111 DPR-25 Amendment No. 122 3.7 LJMITING CQNQlTION FOR 4.7 SURVEILLANCE RE0VIREMENTS OPERATION (Cont'd.)

(Cont'd) c.

At least once per quarter:

(1) All normally open power-operated isolation valves (except for the main steam line power-operated isolation valves) shall be fully closed and reopened.

(2) With the reactor power less than 50X of rated, trip main steam isola-tion valves (one at a time) and verify closure time.

d. At least twice per week the main steamline power-operated isolation valves shall be exercised by partial closure and subsequent reopening, 2, In tne event any primary

2. Whenever a primary containment containment isolation valve isolation valve or any reference or any reference leg leg backfill check valve is backfill check valve inoperable, the position of at becc.mes inoperable, reactor least one other valve in each power operation may line having an inoperable valve continue provided at least shall be recorded daily, one valve in each line having an inoperable valve is in the mode corresponding to the isolation condition.

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3/4.7-28 l

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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COMMONWEALTH EDISON COMPANY f.%

J0WA-ILLINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 M@ CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.1;E License No. DPR-29 ite Nuclear Regulatory Commission (the Commission) has found that:

2.

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated March 11, 1994, 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; F

7t+ f acility 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:

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 amendment and paragraph 2.C.(2) of. Facility Operating License No. DPR-19 is hereby amended to read as follows:

2-Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.148, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

inis license amendment is effective as of the date of its issuance; to La implemented within 30 days.

FOR THE NUCLEAR REGULA10RY COMMISSION Y N O. 0,E - Y Robert A. Capra Director Project Directorate 111-?

Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation

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ATTACHMENT TO LICENSE AMENDMENT NO. 14' FACILITY OPERATING LICENSE NO. DPR-29 QQ{KET NO. 50-254 Resi;c the Appendix A Technical Specifications by removing the pages idtntified below and inserting the attached pages. The revised pages are iden6ified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 3.7/4.7-18 3.7/4.7-18 3.7/4.7-19 3.7/4.7-19 l

I

QUAD CITIES DPR-29 c

hv activity is being performed c.

Secondary containment capability which can reduce the shutdown to maintain an average 1/4 inch of margin below that specified in water vacuum under calm wind Specification 3.3.A.

(2<0<5 mph) conditions with a filter train flow rate of not more d.

The fuel cask or irradiated than 4000 cfm shall be fuel is not being moved in the demonstrated at each refueling reactor building, outage prior to refueling.

2.

The doors of the core spray and 2.

Whenever the LPCI mode of the RHR and RHR puro compartments shall be core spray subsystems are required to closed at all times except during be operable, the doors of the core patsaae & order to consider the spray and RHR pump compartments shall

. r- ::

. system and LPCI mode of be verified to be closed weekly.

• r-

-.. stem operable.

s-

:ation 3.7.C.1 cannot be

• "rWas shall be initiated a

(

-!,:n conditions listed in a;m 1 'c ot ions 3.7.C.) a through j

D P i-

P

• .C -~;-t helation Valves D.

Primary Containment isolation Valves 1.

During re3c'.or power operating 1.

The primary containment isolation cond* t ions. all isolation valves valves surveillance shall be l i s *, e d i r. 'able 3. 7-1, all performed as follows:

instrunnt line flow check valves which contact the primary coolant a.

At least once per operating system and all reference leg cycle the operable isolation backfill check valves shall be valves that are power operated operable except as specified in and automatically initiated Specification 3.7.D.2.

shall be tested for simulated automatic initiation and closure times.

3.7/4.7-18 Amendment No.148

QUAD CITIES DPR-29 f

b.

At least once per operating cycle the instrument line flow check valves shall be tested for proper operation.

c.

At least once per quarter:

1) All normally open power operated isolation valves (except for the main steamline power-operated isolation valves) shall be fully closed and reopened.

2)

The main steamline isolation valves (one at a time) shall be verified for closure time.

2 Ir t*t event any isolation valve 2.

When an isolation valve listed in ur ified in Table 3.7-1 or any Table 3.7-1 or a reference leg r< erence leg backfill check valve backfill check valve is becc~cs inoperable, reactor power inoperable, the position of at operation nay continue provided at least one other valve in each line

+r r

0. a in each line having an inoperable valve shall a.;r; c.

naperable valve is in be recorded daily.

the mode corresponding to the isolated condition.

3.

If Specifications 3.7.D.] and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold stutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.7/4.7-19 Amendment No.148

O 8

UNITED ST ATES NUCLEAR REGULATORY COMMISSION

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{_0MMONWEALTH EDISON COMPANY a!!D 10WA-ILLIN015 GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FAtill1Y OPERATING LICENSE Amendment No. 144 License No. DPR-30 1.

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

I.

The application for amendment by the Commonwealth Edison Company (the licensee) dated March 11, 1994, 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; The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; t.

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; 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 amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:

~

. B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 144, 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; to be implemented prior to restart following the 13th refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION N O.

Robert A. Capra, Director Project Directorate 111-2 Division of Reactor Projects - lil/lV Office of Nuclear Reactor Regulation A ; I a,; n- ( r, t.

Changes to the Technical

$0V;1'i Cptlens Date of !sivance:

f, 1992

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1 ATTACH 4ENT TO LICENSE AM(fiDMllG_30.141

[AClllTY OPERATING LICENSE NO. OPR-30 DOCKET NL 50-265

. n tN Appendix A Technical Specifications by reinoving the pag?s

. * ad below and inserting the attached pages.

Thc revised pages are

.u.nt it led by the captioned amendment number and contain uarginal lines indic6'.snr the area of change.

PEMOVE INSERT 3.7/4.7-9

3. 7/4. 7-9 3.7/4.7-10 3.7/4.7-10 3.7/4.7-10a

QUAD CITIES DPR-30 reactor water temperatv e b.

Additional tests shall be 5 below 212'r and the reactor performed during the first coolan' systems ar) vent 9d.

operating cycle under an adequate number of different environmental wind conditions to enable valid extrapolation of the test results.

No activity is being performed c.

Secondary containment wrich can reduce the shutdown capability to maintain an raryin below that specified in average 1/4 inch of water.

Stecification 3.3.A.

vacuum under calm wind (2<0<5

.:,) conditions with a filter fuel cask or irradiated tvain flow rate c' no* nore is not being moved in the than 4000 cfm shall be

• or building, demons

• rated at each returning outage prior to refuel na.

of the core spray and 2.

khenever the LPCI mode of the Rl1 re-t,.

compartments shall be and core spray subsystems are

'ic'*

all times except during required to be operable, the do*+'.

ut.s; i t. order to consider the of the core spray and RHR pump rerc <rri system and LPCI mode of compartments si41' ce verified tre io,jstem operable.

be closed weekly, e

.. =i :stion 3.7.C.1 cannot be rot pro:edures shall Le initiated

't es,elish conditions listed in 5;e:'i tations 3.7,0.1 + through 0.

D.

Primary Containmont Isolation Valves D.

Primary Containment Isolation ValvJs 1.

During reactor power operating 1,

The primL y containment isolation conditinns, all isolation valves valves surveillance shall be listed in lable 3.7-1, all performed as follows:

instrument line flow check valves which contact tt3 primary coolant a.

At least once per operatint-system and all reference leg cycle the operable isolation backfill check valves shall be valves that are power oprrated operable except as specified in and automatically tr ~1';

,4 Specification 3.7,0.2.

shall be tested f or simiu 'zi automatic initiation and closure times.

3.7/4.7-9 Antndment No.144

QUAD CITIES DPR-30 b.

At least once per operating cycle the instrument line flow check valves shall be tested for proper operation.

c.

At least once per quarter:

1) All normally open power operated isolation valves (except for the main steamline power-operated isolation valves) shall be fully closed and reopened.

2) The main steamline isolation valves (one at a time) shall be verified for closure time.

2 lr **, eve t any isolation valve 2.

When an isolation valve listed in spu,f'ed in Table 3.7-1 or any Table 3.7-1 or a reference leg raference lea backfill check valve backfill check valve is ceco es 'noperable, reactor power inoperable, the position of at ter' inue provided at least one other valve in each line

• ^*-

itast :nt - s'se ir, each line having an inoperable valve shall having an ircre able valve is in be recorded daily.

the rode ctrrc5;inding to the iso'ated condt11,n.

3.

If Specifications 3.7,0.1 and 3.7 D.2 cannot be act, ar orderly shutdown shal! ce i1*i. lated and the reactor shall be n the cold shutdown condition v 1.hir ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4.

The temperature of the main steamline air pilot valves shall be less than 170*F except as specified in Specifications 3.7.0.5 and 3.7,0.6 below.

3.7/4.7-10 Amendment No.144

QUAD ClllES DPR-30 5.

from and after the date that the temperature of any main steamline air ;ilot valve is found to be greater than 170'F, reactor operation is parmissible only cur'ng the succeeding 7 days unless the temperature of such valve is sooner reduced to less than 170 F provided the main sicamline isolation valves are operable.

.' f 3; t-

' f i c a t ion 3. 7.0. 5 cannot be t'

ain steamline isolation

.; ' o-s r ail be considered rJ 'e and action taken in

'e*r'-

with Specification L

1 3.7/4.7-10a Amendment No.14 1

....