ML20003F694

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Revised Tech Spec Pages 3.7/4.7-2,3.7/4.7-3 & 3.7/4.7-4 for Licenses DPR-29 & DPR-30
ML20003F694
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/13/1981
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20003F692 List:
References
NUDOCS 8104230419
Download: ML20003F694 (8)
v • d • e


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O Attachment 1 Quad Cities Station Unit I h Proposeo Amendment to Technical Specifications for F a c i l i t ,- Operating License DPR-29 Revised Pages: 3.7/4.7-2 3.7/4.7-3 3.7/4.7-4 i

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8104230419

QUAD CITIES DPR-29 power operation ' limit specified in Item 1.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 f rom any operating condition it the pool temperature reaches i100F. 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 ratet if the pool temperature reaches 1200F.

d. Maximum oowncomer Submergence 3.54 fL.
e. Minimum downcomer Submergence 3.21 ft.
2. Primary containment integrity shall 2. The containment leakage rates shall be maintained at all times when the be demonstrated at: the. following reactor is critical or when the test schedule,

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and' shall be reactor water temperature is above determined . in conformance with the l 2120F and fuel is in the reactor criteria specified in -Appendix J of vessel except while perf orming low 10 CFR 50 using' the methods and l' provisions of ANSI N45.4 (1972).

power physics tests at atmospheric l 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 containment leakage rates shall shutdown at either Ps a 48 l be limited to: psig, or at P, t 25 psig during I 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) $ La, 0.75 percent by -inspection.

weight of the containment

!- dir 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 l

i 3.7/4.7-2 l'

QUAD CIIIES OPR-29 b) 6L, t 0.75 percent by b. It any . periodic Type ~ A- test 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 a fails to meet either 0.75 La or 0.75 L, t the test schedule reduced pressure of P, t for subsequent Type A . tests 25 psig. shall be reviewed and approved by the comission. If two

2) A combined leakage rate of consecutive Type A tests f ail to 6 0.60 La for all meet either- 0.75 La or 0.75 penetrations and valves, L,t a Type A test shall be except for main steam perf ormed 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- La or 0.75 L, t 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 verif ied by a

b. With the measured overall supplemental test which:

integrated containment leakage rate exceeding 0.75 La or 0.75 l) Confirms the accuracy of the L,t as applicable, restore the test by verifying that the overall integrated leakage difference between the rate (s) to t< 0.75 La or 5 0.75 supplemental data and the L t , as applicable. Type A test. data is within 0.25 La or 0.25 Lt-

c. With t ',e measurea combined leakage rate for all 2) Has a duration sufficient to penetrations and valves, except establish accurately. the-tor 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 f or main stear.1 isolation valves, injected into the contJinment subject to Type B and C tests or bled from the containment to 6 0.60 La. during the supplemental test to be equivalent to at least

d. With the measured leakage rate 25 percent of- the total exceeding 11.5 scf per hour for measured leakage at Pa, 48 any one main steam isolation psig, or P t , 25 psig.

valve, restore the leakage rate to 511.5 scf per hour for any a. Type B and C tests shall be-one main steam isolation valve conducted at Pa, 48 psig, at prior to increasing the reactor intervals no greater than 24 coolant temperature above months except for tests 2120F. involving:

1) Air locks, which shall be tested at 10 psig at least once per 18 months, and
3. 7 /4 . 7-3

QUAD CITIES 10PR-29

2) Main -steam isolation valves, which .shall be leak tested at least once per 18 months.at.a pressure of 25 psig.
e. All test leakage rates! shall be

.CdlCulated using observed . data converted to -absolute ~ values.

Error analyses shall Le.

performed ' to- se lect- a balanced integrated leakage measurements system.

f. . Continuous' Leak Rate Monitte-
1) When the primary containment is inerted, the containment shall be. continuously monitored- for' gross leakage byf~ review of the inerting-system makeup requirements.
2) This- monitoring system may be taken out of service for the purpose of Imaintenance 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 Vacuum Breakers
a. Except as- specif ed in a. The pressure suppression Specification 3.7.A.3.b below, chamber-reactor building vacuum two pressure sup-
3. //4. /-4

Attachment 2 Quad Cities Station Unit 2 Proposed Amendment to Technical Specifications for Facility Operating License DPR-30 Revised Pages: 3.7/4.7-2 3.7/4.7-3 3.7/4.7-4 I

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QUAD CITIES DPR-30~

power operation limit specified in Item l 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 poci
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 i 150 psig at normal cool-down i

rates if the pool temperature reaches 1200 F.

d. Maximum downcomer Submergence 3.54 ft.
e. Minimum downcomer Submergence 3.21 ft.
2. Primary containment integrity shall 2. The containment leakage rates shall '

be maintainea 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 conf ormance 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 exceeo 5 MWt. a. Three Type A tests (Overall

' Integrated- Containment Leakage

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

i integrity is required, primary 10 month- intervals during

, containment leakage rates shall shutdown at either Pa, 48 i be limited to: psig, or at P, t 25 psig during 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) 6 La, 0.75 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 3.7/4.7-2 i' _ _

_ - -. --- ~ - -- - - - >

e QUAD CITIES DPR-30 b)- 6L, t 0.75 .percent by b. If any periodic Type A test weight of the containment fails to meet either 0.75 La 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,t the test schedule reduced pressure of P, t for subsequent . Type A tests 25 psig. shall be reviewed and approved by the commission. If two

2) A combined leakage rate of consecutive Type A tests f ail to 4 0.60 La for all meet either 0.75 L a or 0.75 penetrations and valves, L,t 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 a or 0.75 L, t 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 overall supplemental test which:

integrated centainment leakage rate exceeding 0.75 La or 0.75 1) Confirms the accuracy of. the L,t as applicable, restore the test by verifying that the overall integrated leakage difference between the rate (s) to 6 0.75 La or 6 0.75 supplemental data and the i L t , as applicable. Type A test data is within 0.25 La or 0.25 Lt -

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 L, a restore the the supplemental test.

wmbined 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 8 and C tests or bled f rom the containment to 4 0.60 La . during the supplemental test to be equivalent to r least

d. With the measured leakage rate 25 percent of th< total exceeding 11.5 scf per hour for measured leakage at .Pa, 48 any one main ste m isolation psig, or Pt, 25 psig.

valve, restore the leakage rate to $ 11.5 scf per nour for any d. Type B and C tests shall be one main steam isolation valve conducted at P, 3 48 psig, at prior to increasing the reactor intervals no greater than 24 tests

! coolant temperature above months except for 2120F. involving:

1) Air locks, which shall be tested at 10 psig at least once per 18 months, and 3.7/4.7-3

. o QUAD CITIES

'DPR-30

2) Main . steam isolation valves, which shallibe leak tested ~at least once per -18. months at a -

pressu're of 25 psig.

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

Error- shall analyses be

- performed to select 'a balanced?

integrated leakage measurements system.

f. Continuous t.eak Rate Monit'or f 1)- When .-the primary containment i- is inerted, the. containment
shall . be continuously monitored forLgross -leakage

i by. review :of the inerting 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 servicef as' soon as

! practical.

3. Pressure Suppressior. Chamber . 3. Pressure Suppression Chamber-Reactor Building Vacuum Breakers Reactor Building Vacuum Breakers
a. Except as specified in a.-The pressure suppression j' Specification 3.7.A.3.b below, chamber-reactor building vacuum two pressure sup-I 3

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