ML20082J868
| ML20082J868 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/23/1991 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082J869 | List: |
| References | |
| NUDOCS 9108290044 | |
| Download: ML20082J868 (11) | |
Text
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION
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TOLEDO EDISON COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSF NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. If'0 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric illuminating Company (the licensees) dated March 1, 1991 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; B.
The facility 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 compli nce 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9100290044 910023 PDR ADOCK 05000346 s
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(a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.160, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
on B. Hopkins, Sr. Project Manager Project Directorate 111 3 Division of Reactor Projects 111/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 23, 1991 l
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i ATTACHMENT TO LICENSE AMENDMENT NO.160 l
t FACILITY OPERATillG LICENSE NO. NPF-3 DOCKET NO. 50-346 i
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 6-2 3/4 6-2 l
3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 j
3/4 6-5 3/4 6-5 B 3/4 6-1 B 3/4 6-1 i
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3/4.6 CONTAINMENT SYSTEMS 3]4.6.1 PPlMARY CONTAlf4 MENT CONTAINMENT INTEGRITY L IMITING CONDITION FOR OPERATION 3.6.1.1 Primary C0f4TAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMEf4T INTEGRITY, restore CONTAINMENT INTEGRITY 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 SHU1DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRlTY shall be demonstrated:
a.
At least once per 31 days by verifying that:
1.
All penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except those valves that may be opened under administrative controls per Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealed, b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that verification of these penetrations being closed need not be performed more of ten than once per 92 days.
Amendment No. 147 DAt'5-BESSE, UNIT 1 3/4 6-1
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPEPATION 3.6.1.2 Containment leakage rates shall be limited to:
L, 0.50 percent by a.
An overall integrated leakage rate of 1 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 P,, 38 psig, b.
A combined leakage rate of < 0.60 L, for all penetrations and a
valves subject to Type B an3 C tests, when pressurized to P -
a c.
A combin M leakage rate of 1 0.03 L for all penetrations thataresecondarycontainmentbypa$sleakagepaths,when pressurized to P '
a d.
A single penetration leakage rate of 1 0.15 La for the contain-ment purge and exhaust isolation valve special test.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, or (c) with the combined bypass leakage rate exceeding 0.03 La, restore tne leakage rate (s) to l
within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.
b.
With a single containment purge and exhaust isolation valve penetration having leakage rate exceeding 0.15 L t restore the g
leakage rate to within limits in 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 /> 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 />.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confonnance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at P, 38 psig, during each To year service period.
a DAVIS-BESSE, UNIT 1 3/4 6-2 Amendment No. 97, AM;,160 l.
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CONTAINMENT SYSTEMS l
SURVEILLANCE REQUIREMENTS (Continued) j i
b.
If-any periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be reviewed an8, approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L TypeAtestshallbeperformedatleastevery18monthsuntiltw$,a consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed.
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confinns the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within t
0.25 L,.
2.
Has a duration sufficient to establish accurately the change in i
leakage between the Type A test and the supplemental test.
l 3.
Requires that the rate at which gas is injected into the containment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L
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d.
Type B and C tests shall be conducted with gas at P, 38 psig, at intervals no greater than 24 months except for test $ involving air locks.
e.
The combined bypass leakage rate shall be determined to be < 0.03 L l
a by applicable Type B and C tests at least once every 24 months j
except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable lealage when tested with soap bubbles while the contain-ment is pressurized to P,, 38 psig, during each Type A test.
i f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance l
Requirement 4.6.1.3.
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DAVIS-BESSE, UNIT 1 3/4 5-3 Amendment No. 90,UD,160
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l g.
Each time the containment purge and exhaust isolation valves are l
opened, a special test shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after valve closure or prior to entering MODE 4 from MODE 5, whichever j
is later. The special test is conducted by pressurizing tne piping section including one valve inside and one valve outside the containment to a pressure greater or equal to 20 psig.
The leakage rate per penetration shall not exceed 0.15 L
- a h.
The special test as defined in Surveillance Rec,;irement 4.6.1.2 9 l
shall be perfomed for the containment purge and isolation valves when the plant has been in any combination of MODES 3, 4, 5 or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the test required *by Surveil-lance Requirement 4.6.1.2.g has not been perfomed in the previous 6 months.
1.
All test leakage rates shall be calculated using observed data l
converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
J.
The provisions of Specification 4.0.2 are not applicable.
l DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90, 160 i
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TABLE 3.6-1 l
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DAVIS-BESSE,-UNIT 1 3/4 6-5 Amendment No.160 I
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CONTAINMENT SYSTEMS g NTAINMENT AIR _ LOCKS
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LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
Both doors closed except when the air lock is being used for a.
normal transit entry and exit through the containment, then at j
least one air lock door shall be closed, and l
l b.
An overall air lock leakage rate of < 0.002 L, at P,, 38 psig.
APPLICABillTY: MODES 1, 2, 3 and 4.
ACTION:
j i
With an air lock inoperable, restore the air lock to OPERAE'LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> 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 />, j
I SURVEILLANCE REQUIREMENTS i
t 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
'Af ter each opening except when the air lock is being used for a.
multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying
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either no detectable seal leakage when the volume between the i
door seals is pressurized to 10 psig, or by verifying a seal leakage rate of < 0.0015 L seals is pressurTzed to P, when the volume between the door f
holddowns are installed.,, 38 psig, and the air lock door l'
b.
At least once per 6 months by conducting an overall air lock
[
1eakage test at P 38 psig, and by verifying that the overall j
air lock leakage fa,te is within its limit, and At least once per 6 months by verifying that only one door in l
c.
eacn air lock can be opened at a time, t
Exemption to Appendix "J" of 10 CFR 50.
DAVIS-BESSE, UNIT 1 3/4 6-6 l
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3/4.6 CONTAINMENT SYSTEMS BASES I
3/4.6.I PRIMARY CONTAINMENT l
3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive i
materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses, i
This restriction, in conjunction with the leakage rate limitation, will l
limit the site boundary radiation doses to within the-limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE I
The limitations on containment leakage rates ensure that the total f
containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 38 psig P. As an j
a added conservatism, the measJred overall integrated leakage rate is further limited to 1 0.75 L, during performance of the periodic tes,s
[
p to account for possible degradation of the containment leakage barriers j
between leakage tests, i
The surveillance testin1 for measuring leakage rates are consistent I
with the requirements of 10 CFR Part 50, Appendix J with the following exemption.
The third test of each Type A testing set need not be conducted i
when the plant is shutdown for the 10-year plant inservice inspections, The operational readiness of the vessel is considerN proven by the ILRT, and in accordance with license requirements, when completed per the 40 +
10 months frequency.
j The special test for the containment purge and exhaust isolation valves is intended to detect gross degradation of seals on the valve I'
seats.
The special test is pW foned in addition to the Appendix J requirements.
')SAR 6.2.4 icentifies all penetrations that are secondary containment L
bypu.s leakage paths.
3/4.6.1.3 CONTAINMENT AIR LOCKS f
The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become r
i excessive due to seal damage during the intervals between air lock leakage tests.
DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. 90,H5,160 f
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CONTAINMENT SYSTEMS
, BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.
The maximum peak pressure obtained from a LOCA event is 37 psig.
The limit of 1 psig for initial positive containment p: essure will limit the total pressure to 38 psig which is less than the design pressure and is consistent with the safety analyses.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that j
the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA.
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contain-ment steel vessel will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 38 psig in the event of a LOCA. A visual inspection in conjunction with Type A leikage tests is sufficient to demonstrate this capability.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The limitation on use of the Containment Purge and Exhaust System limits the time this system may be in operation with the reactor coolant system temperature above 200'F.
This restriction minimizes the time that a direct open path would exist from the containment atmosphere to the outside atmosphere ar.. consequently reduces the probability that an accident doseNould exceed 10 CFR 100 guideline values in the event of a LOCA occurring coincident with purge system operation.
The use of this system is therefore restricted to non-routine usege not to exceed 90 l
hours in any consecutive 365 day period which is equivalent to approximately 1% of the total possible yearly unit operating time.
3/4.6.2 DEpRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray syst s ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No.135 i
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