ML20063P960
| ML20063P960 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/09/1990 |
| From: | Wechselberger Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063P961 | List: |
| References | |
| NUDOCS 9008160055 | |
| Download: ML20063P960 (16) | |
Text
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UNITE 0 87 ATE 8 NUCLEAR REGULATORY COMMISSION 5
wAsmotou,0. c. scoes COMMONWEALTH EDISOM COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION UNIT 2 4
AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.112 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated July 31 1990, complies with the standards and.requirementsoftheAtomleEnergyActof1954 as amended.
(the Act), and tne Comission's rules and regulations set forth in 10 CFR Chapter I; 1
B.
The facility will o)erate in conformity with the tpplication, the provisions of t.1e Act and the rules and regulations of the
- Comission; C.
There is reasonable assurance (1) that the activities authorized i
by this amendment can be conducted without endangering the health i
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.
2.
AccordinglyI the license is amended by changes to the Technical Specifi-cations as ndicated in the attachment to tais license amendment and 4
paragraph 3.8. of Provisional Operating License No. DPR-19 is hereby l
amended to reid as follows:
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,- B.
Technical Specifications The Technical Specifications cortained in Appendix A, as revised through Amendment No. 112 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 C0fHISSION Jacob F. Wechse erger,ActIngDirector Project Directorate 111-2 Division of Reactor Projects - !!!,
IV, V.and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 9, 1990 I
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e ATTACHMENT TO LICENSE AMENDK,. NO. 112 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Revise 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 stea of change.
REMOVE INSERT 3/4.7-6 3/4.7-6 3/4.7-7 3/4.7-7 3/4.7-8 3/4.7-8 3/4.7-9 3/4.7-9 3/4.7-9a r
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DRESDEN II DPR-19 Amendment No. 112 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
(1) An overall integrated leakage rate for Type A tests of:
(t,) L less tRInor equal to 75
,?ercent of L,.
The RBCCW pathway described in Section 4.7.A.2.e.(4) is excluded until the end of the Cycle 12 refueling outage.
(b) L less tbInor equal to 75 percent of L*
t (2) (a) A combined leakage rate of less than I
or equal to 60 percent of L for alltestable penetrations and isola-tion valves subject to Type B and C tests ex-cept for main s'.eam isolat on valves.
The RBCCW pathway described in Section 4.7.A.2.e.(4) is also excluded until the end of the cycle 12 refueling outage.
3/4.7-6 J
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DRESDEN li DPR-19 Amendment No. 112 3.7 LIMITING CONDITION FOR OPEP.ATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
1 (b) A leakage rate of less than or equal to t
3.75 percent 1
of L for any$neair lock when pressur _ed to 10 psig.
(c) 11.5 SCF per hour
)
for any main steam isolation valve at a test pressure of l
25 psig.
c.
If two consecutive Type A tests fail to meet either 75 percent of L or 75 percent of L,
aTypeAtestsball be performed at each
> shutdown for re-fueling or approx-imately every 18 months until t;.'
consecutive Type A tests meet.the above requirements, at which time the normal test sched-ule may be resumeJ.
d.
The accuracy of each Type A test shall be verified by a supplemental test which:
3/4.7 !
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DRESDEN II DPR-19 Amendment No. 112 i
3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
) Confirms the accuracy of the test by verify-ing that the difference be-tween the supplemental-data and the Type A test data is within 25 percent of L or 25 p$rcent of L
- t (2) Has a duration sufficient to establish accurately the change in leakage rate between the
. Type A test and the supplemental test.
(3) Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to i
at least 9 scfm.
e.
Type B and C tests shall be conducted at P, at intefvalsno greater than 24 months except for
. tests involving:
3/4.7-8
I DRESDEN II DPR-19 l
Amendment No. 112 l
t 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS l
(Cont'd.)
(Cont'd.)
(1) Main steam line isolation i,
valves which shall be tested i
at a pressure of 25 psig each operating cycle.
(2) Bolted l
double gasketed seals which shall be tested at a pressure of 48 psig-whenever the seal is closed after being opened and each operating cycle.
(3)- Air locks which shall be tested I
at 10 psig each operating cycle.
(4) The Reactor Build-ing Closed Cooling f
Water (RBCCW) inlet pathway to l
the primary con-tainment (penetra-tion X-123) will not be tested until the end of the
-Cycle 12 refuel-ing outage.=
i f.
Continuous Leak Rate Monitor (1) When the primary containment is inerted, the containment 3/4.7-9 l
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l DRESDEN 11 DPR-19 l
Amendment No. 112
- l. 7 LIMITING CONDITION FOR OPERATION 4.7 $URVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
shall be continuously monitored for gross leakage by review of the inerting system make-up 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.
g.
The interior surfaces of the drywell shall be visually inspected each operating l
cycle for evidence of deterioration.
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~ -. -. - -...-. - -.
p **e 8
'g UNITED STATES i
NUCLEAR REGULATORY COMMISSION n
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wasmwoTow, n. c. rosos COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE
. Amendment No. 108 License No. DPR-25 l
1.
The Nuclear Regulatory Comission'(the Comission) has found that:
f A.
The application for amendment by the Commonwealth Edison Company (thelicensee)datedJuly 31, 1990, 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 Chapter I; B.
The facility will o>erate in conformity with the application.
the provisions of t1e Act and the rules and regulations of the Comission, C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public,ith the Comission's regulations; and(ii)thatsuchactivitieswillbe conducted in compliance w 2
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 Comission's regulations and all applicable requirements have been satisfied, j
L 2.
AccordinglyIndicatedintheattachmenttothislicenseamendmentand' the license cations as paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
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2 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.108, are hereiy. 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 D
Jacob F. Wechselb ger, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications t
Date of Issuance: August 9, 1990 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 108 i
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FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 i
Revise the Appendix A Technical Specifications by removing the pages' identified l
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' 3/4.7-6 3/4.7-6 3/4.7-7 3/4.7-7 3/4.7-8 3/4.7-8' l
3/4.7-9 3/4.7-9 i
3/4.7-9a t
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DRESDEN III DPR-25'
)
Ament. ment No. 108 s
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1 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS I
? Cont'd.)
(Cont'd.)
1 (1) An overall j
integrated 1
leakage rate i
t for Type A tests of:
(a) L less J
t$Inor equal to 75 percent of L,
The RBCCW p$thwayde-q scribed in Sec-tion 4.7.As2.e(4) is excluded until the end of the i
Cycle 12 refuel-i ing outage.
(b) L less tbInor equal to 75 l
percent of L*
t i
(2) (a) A combined r
leakagt rate of less than or equal to 60 percent of L for I
allfestable penetrations and isola-tion valres subject no Type B ani C tests except l
for main l
steam isola-tion valves.
The RBCCW path-vay described in Section 4.7.A.2.e.(4) is also excluded i
l until the end of Cycle 12 refueling outage.
3/4.7-6 v
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f *
'DRESDEN III DPR-25 Amendment No.
108 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
l (b) A leakage rate of less than or i
equal to 3.75 percent of L for=
any8neair lock when pressurized to 10 psig.
(c) 11.5 SCF per hour for any main steam isolation valve at a test pres-sure of 25 psig.
c.
If two consecutive Type'A tests fail to meet either 75 percent of L or 75 percent of L '
t a Type A test shall be performed at each shutdown for refueling or approximately every 18 months until two consecutive Type A 4
tests meet the above requirements, at which time'the normal test sched-ule.may be resumed..
d.
The accuracy of
'[
each Type A test shall be verified by a supplemental-test which:
t (1) Confirms the accuracy of the test by
. verifying that the difference.
3/4.7-7 4
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f'.
E DRESDEN III DPR-25 Amendment No.
108 l
l
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3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
I between the supplemental data and the Type A test.
data.is within f
25 percent of L or 25
=p$rcentofL' t
(2) Has-a duration.
i sufficient to establish accurately the i
change in i
leakage rate between the Type A test and the supple-mental test.
(3) Requires the l'
quantity of'.
gas injected i
into the con-
.l tainment or
' bled from the containment-during the supplemental e
test to be i
equivalent to at least 9 i
scfm.
e.
Type B and C tests shall be conducted at P, at inter-vals*no greater
.than 24 months except for tests t
involving:
(1) Main steam line isola-v tion valves-which shall be tested at a pressure of 25 psig.each operating cycle.
3/4.7-8
DRESDEN III.
]
Amendment No. 108
]
3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
t (2) Bolted double-i gasketed seals
(
which shall be tested at a pressure of i
48 psig whenever the seal is closed after being opened and
)
each operating cycle.
(3) Air locks which shall be tested at 10 psig each operating cycle.
i (4) The reactor Building Closed Cooling Water (RBCCW) inlet pathway to
'the primary containment (penetration X-123) will not be tested until the end of the Cycle 12' refueling
- outage, f.
Continuous Leak i
Rate Monitor.
(1) When the primary con-tainment is inerted, the containment shall be continuously monitored for gross leakage by review of th;'inerting system make-up 4
requirements.
i f
3/4.7-9 a
~
DRESDEN III DPR-25 Amendment No. 108 i
i i.
3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS IDont'd.)
(Cont'd.)
l (2) This monitoring system may be 5
taken out of service for the
_ purpose of maintenance or testing but shall be returned to service as soon as practical, g.
The interior surfaces of the drywell shall be visually inspected each operating cycle for evidence of deterioration.
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