ML20066C786

Amends 82 & 76 to Licenses DPR-29 & DPR-30,respectively, Providing for Primary Containment Integrated Leak Rate Test Requirements & Schedules Consistent W/App J to 10CFR50

ML20066C786
Person / Time
Site:	Quad Cities   (DPR-029, DPR-030)
Issue date:	11/02/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Commonwealth Edison Co, Iowa Illinois Gas & Electric Company
Shared Package
ML20066C787	List: ML20066C786 ML20066C788 ML20066C795
References
DPR-29-A-082, DPR-30-A-076 NUDOCS 8211100445
Download: ML20066C786 (12)

Text

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[p.a nouq(o UNITED STATES NUCLEAR REGULATORY COMMISSION

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COMMONWEALTH EDISON COMPANY AND b

IOWA ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION UNIT NO. 1 7

AMENDMENT TO FACILITY 0PERATING LICENSE Amendment No. 82 License No. DPR-29 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated April 13, 1981, as supplemented December 2, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in confonnity with the application, B.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.

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; The issuance of this am'e'ndment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

51 of the Commission's regulations and all applicable requirements i

have been satisfied.

Accordingly, the license is amended by changes to the Technical Spec-2.

ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-29 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

P

l 1 3.

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

FOR THE NU LEAR REGULATORY COMMISSION Domenic B. Vassal 16, Chief Operating Reactor's Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specificctions l

Date of Issuance: November 2, 1982 e

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1 Attachment to License Amendment No. 82 To Facjlity Operating Licente DPR' 29 ~

Docket No. 50-254 Revise Appendix A Technical Specifications as follows:

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QUA0 CITIES OPR-29 i

powe r operation limit specified in Item I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3) The reactor shall be scrammed from any operating condition if the pool temperature 0

reaches 110 F.

Power operation shall not be resumed until the pool temperature is reduced below the normal operation limit specified in Item 1.

4) During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 150 psig at normal cool-down rates.if the pool temperature reaches 1200F.

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o. Maximum downcomer Submergence 3.54 ft.

c. Minir.um downcomer Submergence 3.21 ft.

2. Primary containment integrity shall

2. The containment leakage rat'es shall be maintained at all times when the be demonstrated at the following reactor is critical or when the test schedule, and shall be reactor water temperature is above determined in conformance with the 2120F and fuel is in the reactor criteria specified in Appendix J of vessel except while performing low 10 CFR 50 using the methods and power physics tests at atmospheric provisions of ANSI N45.4 (1972).

' pressure at power levels not to exceed 5 MWt.

a. Three Type A tests (Overall Integrated Containment Leakage l

a. When primary containment Rate) shall be conducted at 40 integrity is required, primary 10 month intervals during containment leakage rates shall shuf: d c -

at either Pa, 48 be limited to:

psig, c.

6t Pt, 25 psig during each 10-year service period.

1) An overall integisted leakage The third test of each set shall rate of:

be conducted during the shutdowr for the 10-year plant inservice a) 6L, 1.0 percent by inspection.

a weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at, Pat 48 psig, or 1

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3.7/4.7-2 Amendn nt No'. 36 82

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QUAD CITIES DPR-29 b) $ L, 1.0 percent by b.

If any periodic Type A test t

weight of the containment f ails to meet either 0.75 La air per 24 nours at a or 0.75 L, the test schedule t

reduced pressure of P,

for subsequent Type A tests t

25 psig, shall be reviewed and approved by the commission.

If two

2) A combined leakage rate of consecutive Type A tests fail tc 60.60 La for all meet either 0.75 La or 0.75 penetrations and valves, L, a Type A test shall be except for main steam performed at least every 18 isolation valves, subject to months until two consecutive Type B and C tests when Type A tests meet either 0.75 pressurized to Pa.

L or 0.75 Lt, at which time the above test schedule may be

3) 11.5 scf per hour for any one resumed.

main steam isolation valve

.when tested at 25 psig.

c. The accuracy of each Type A test shall be verified by a

b. With the measured everall supplemental test which:

integrated containe nt leakage rate exceeding 0.75 La or 0.75

1) Confirms the accuracy of the Lt, as applicable, restore the test by verifying that the overall integrated leakage difference between the rate (s) to S 0.75 L or 6 0.75 supplemental data and the-L, as applicable. a Type A test data is within t

c. With the measured combined leakage rate for all

2) Has a duration sufficient.to penetrations and valves, except establish accurately the for main steam isolation valves, change in leakage rate subject to Type B and C tests between the Type A test and exceeding 0.60 La, restore the the supplemental test.

combined leakage rate for all penetrations and valves, except

3) Requires the quantity of gas for main steam isolation valves, injected into the containment subject to Type B and C tests or bled from the containment to 0.60 La.

during the supplemental test to be equivalent to at least d.. Leakage shall be limited to a 25 percent of the total leakage rate of less then or measured leakage at Pa, 48 psig, or P, 25 psig.

equal to 3.75 percent of La t

for any one air lock when pressurized to 10 psig.

d. Type B and C tests shall be conducted at P, 48 psig, at a

intervals no greater than 24 months except for tests involving:

1) Air locks, which shall be tested at 10 psig at least once per 18 months, and -

3.7/4.7-3 Amendment No. 82 m-1 c

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2) Main steam isolation valves,

e. With the measured leakage rate which shall be leak tested at exceeding 11.5 scf per hour for least once per 18 months at a any one main steam isolation pressure of 25 psig.

valve, restore the leakage rate to 611.5 scf per hour for any

3) Bolted double-gasketed seals one main steam isolation valve which shall be tested at a prior to increasing the reactor pressure of 48 psig whenever coolant temperature above the seal is closed after I

I 2120F.

being opened and each l

operating cycle.

e. All test leakage rates shall be calculated using observed data converted to absolute values.

l Error analyses shall be performed to select a balanced integrated leakage measurements system.

f. Continuous Leak Rate Monitor

1) When the primary containment is inerted, the containment shall be continuously monitored for gross leakage i

by review of the 1.nerting system makeup requirements.

2) This monitoring system may be taken out of service for the purpose of maintenance or testing but shall be returned to service as soon as practical.

3. Pressure Suppression Chamber-

3. Pressure Suppression Chamber-Reactor Building Vacuum Breakers Reactor Building Vac0um Breakers I

a. Except as specified in

a. The pressure suppression Specification 3.7.A.3.b below, chamber-reactor building vacuum two pressure sup-

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Amendment No. %$, 82 L

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WASHINGTON, D. C. 20555

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COMMONWEALTH EDIS0N COMPANY AND IOWA ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-265

• QUAD CITIES STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-30 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated April 13, 1981, as supplemented December 2, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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;

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C.

There is reasonable assurance (i) that the activ'ities 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; l

D.

The issuance of this amendment will not be' inimical to the common i

defense and security or to the health and safety of the public; l

and l

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 Spec-l t

ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:

B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated l

accordance with the Technical Specifications.

in the license. The licensee shall operate the facility in l

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3.

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

FOR THE NU EAR REGULATORY COMMISSION

- %wo Domenic B. Vassallo', Chief l

Operating Reactors' Branch iP2 Division of Licensing

Attachment:

Changes to the Technical Specificctions Date of Issuance: Novemter 2, 1982 r

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I Attachment to License Amendment No. 76 To Facility Operating License DPR-30 Docket No. 50-265 i

i Revise Appendix A Technical Specifications as follows:

1 Remove Insert 3.7/4.7-2 3.7/4.7-2 3.7/4.7-3 3.7/4.7-3 l

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sp QUAD CITIES DPR-30 power operation limit specified in Item 1 within 24

hours,

3) The reactor shall be scrammed from any operating condition if the pool temperature.

reaches 1100F.

Power operation shall not be resumed until the pool temperature is reduced below the normal operation limit specified in Item 1.

4) During reactor isolation conditions, the reactor pressure vessel shall be depressurized to less than 150 psig at. normal cool-down rates if the pool temperature reaches 1200F.

l

o. Maximum downcomer Submergence 3.54 ft.

e. Minimum downcomer Submergence 3.21 ft.

2. Primary containment integrity shall

2. The conta'inment leakage rates shall be maintained at all times when the be demonstrated at the following reactor is critical or when the test schedule, and shall be reactor water temperature is above determined in conformance with the 2120F and fuel is in the reactor criteria specified in Appendix J cf vessel except while performing low 10 CFR 50 using the methods and power physics tests at atmospheric provisions of ANSI N45.4 (1972).

pressure at power levels not to exceed 5 MWt.

a. Three Type A tests (Overall Integrated Containment Leakage

a. When primary containment Rate) shall be conducted at 40 +

integrity is required, primary 10 month intervals during

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containment leakage rates shall shutdown at either Pa, 48 be limited to:

psig', or at P, 25 psig during t

each 10-year service period.

1) An overall integrated leakage The third test of each set shall rate of:

be conducted during the shutdown for the 10-year plant inservice a) 5 La, 1.0 percent by inspection.

weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at.Pa, 48 psig, or b.-

Amendment No. H, 76 3.7/A.7-2 e

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QUA0 CITIES DPR-30 b) Jf Lt, 1.0 percent by b.

If any periodic Type A test weight of the containment fails to meet either 0.75 L air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a or 0.75 L, the test schedufe t

reduced pressure of P,

for subsequent Type A tests t

25 psig.

shall be reviewed and approved by the cogmission.

If two

2) A combined, leakage rate,of consecutive Type A tests fail tc 5 0.60 La for all meet either 0.75 La or 0.75 penetrations and valves, L, a Type A test shall be except for main steam performed at least every 18 isolation valves, subject to months until two consecutive' Type B and C tests when Type A tests meet either 0.75 pressurized to Pa.

L or 0.75 Lt, at which time 4

the above test schedule may be

3) 11.5 scf per hour for any one resumed.

main steam isolation valve when tested at 25 psig.

c. The accuracy of each Type A test shall be verified by a

b. With the measured overall supplemental test which:

integrated containment leakage rate exceeding 0.75 La or 0.75

1) Confirms the accuracy of the L, as applicable, restore the test by verifying that the t

overallintegratedleakage difference between the rate (s) to 5 0.75 La or - 0.75 supplemental data and the L, as applicable.

Type A test data is within t

0:25 La or 0.25 L -

t

c. With the measured combined leakage rate for all

2) Has a duration suffici~ent to penetrations and valves, except establish accurately the for main steam isolation valves, change in leakage rate subject to Type B and C tests between the Type A test and exceeding 0.60 La, restore the the supplemental test.

l combined leakage rate for all penetrations and valves, except

3) Requires the quantity of gas for main steam isolation valves, injected into the containment subject to Type B and C tests or bled from the containment to 0.60 La.

during the supplemental test j

to be equivalent to at least

d. Leakage shall be limited to a 25 percent of the total

. leakage rate of less then or measured leakage at Pa, 48 equal to 3.75 percent of La psig, or Pt, 25 psig.

for any one air lock when pressurized to 10 psig.

d. Type B and C tests snall be conducted at P, 48 psig, at a

intervals no greater than 24 months except for tests involving:

1) Air ic:ks, which shall ce tested at 10 psig at least once per 18 months, and -

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Amendnent No. 76 3.7/4.7-3 o

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2) Main steam isolation valves,

e. With the measured leakage rate which shall be leak tested at exceeding 11.5 scf per hour for least once per 18 months at a any one main steam isolation pressura of 25 psig.

valve, restore the leakage rate to f 11.5 scf per hour for any

3) Bolted. double-gasketed seals one main steam isolation valve which shall be tested.at a prior to increasing the reactor pressure of 48 psig whenever coolant temperature above the* seal is closed after 2120F.

being opened and each operating cycle.

e. All test leakage rates shall be calculated using observed data converted to absolute values.

Error analyses shall' be performed to select a balanced integrated leakage measurements system.

f. Continuous Leak Rate Monitor

1) When the primary containment is inerted, the containment shall be continuously monitored for gross leakage by review of the inert.ing system makeuo require,ments.

2) This monitoring system may be taken out of service for the purpose of maintenance or testing but shall be returned to service as soon as practical.

3. Pressure Suppression Chambe,r-

3. Pressure Suppression Chamber-

. Reactor Building Vacuum Breakers Reactor Building Vacuum Breakers l

l a, Except as specified in

a. The pressure suppression Specification 3.7.A.3.b below, chamber-reactor building vacuum two pressure sup-3.7/4.7-4 Amendment No. ~ gg, 76

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