ML20078C139
| ML20078C139 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/17/1995 |
| From: | Gundrum L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078C141 | List: |
| References | |
| NUDOCS 9501260196 | |
| Download: ML20078C139 (9) | |
Text
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49 020
.p UNITED STATES 4
E NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D.C. 20066 4 001
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TOLED0 EDIS0N COMPANY CENTERIOR SERVICE COMPANY AE THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NVCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.194 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 May 1,1992, as clarified by facsimile transmission dated January 10, 1995, 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 previsions 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 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:
t 9501260196 950117 PDR ADOCK 05000346 P
w (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.194, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance t
with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Mo
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Linda L. Gundrum, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 17, 1995 W
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ATTACHMENT TO LICENSE AMENDMENT NO.194 FACILITY OPERATING LICENSE NO. NPF-3 i
DOCKET NO. 50-346 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.
l Remove Insert 1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-3 3/4 6-3 l
1 3/4 6-6 3/4 6-6 j
3/4 6-6a j
B 3/4 6-1 B 3/4 6-1 i
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'I 1
DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1.
Capable of being closed by the Safety Features Actuation System, or 2.
Closed by manual valves, blind flanges, or deactivated automatic valves-secured in their closed positions, except those approved to be open under administrative controls, b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determinatica shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
DAVIS-BESSE, UNIT 1 1-2 Amendment No. 93,135,J47,194
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w 3/4.6 CONTAINMENT SYSTEMS 1
3/4.6.1 -PRIMARY' CONTAINMENT 1
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION i
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3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
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ACTION:
Without prima y CONTAINMENT 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 /> i
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 />.
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SURVEILLANCE REQUIREMENTS j
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated
- a.
At least once per 31 days by verifying inat:
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 i
administrative controls per Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealed.
l b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3
- Except valves, blind flanges, and deactivated automatic valves which are located inside the Shield Building (including the annulus and l
l containment) and are locked, sealed,. or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD l
SHUTDOWN except that verification of these penetrations being closed need not be performed more often than once per 92 days.
i DAVIS-BESSE, UNIT 1 3/4 6-1 Amendment No. /L4J,194 i
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
subsequent Type A tests shall be reviewed and ap, the test schedule for If any periodic Type A test fails to meet 0.75 L proved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, a Type A test shall be performed at least every 18 months until two con,secutive 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.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,.
2.
Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
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,.
d.
Type B and C tests shall be conducted with gas at P,, 38 psig, at intervals no greater than 24 months except for tests involving air locks.
e.
The combined bypass leakage rate shall be determined to be < 0.03 L, by applicable Type B and C tests at least once every 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the contain-ment is pressurized to P,, 38 psig, during each Type A test.
f.
Air locks shall be in compliance with the requirements of Specification 3/4.6.1.3.
DAVIS-BESSE, UNIT 1 3/4 6-3 Amendment No. pp,M p,J$$,194
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CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION i
e OPERABLE with:
3.6.1.3 Each containment air lock shall be l
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of s 0.002 L, at P, 38 psig.
APPLICABILIII: MODES 1, 2, 3 and 4.
ACTION:
- a. With one air lock door inoperable in one or more containment air locks, l
or with the containment air lock interlock mechanism inoperable in one or I
more containment air locks:
1.
Verify an OPERABLE door in each affected air lock is closed i
within one hour, and
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2.
Lock an OPERABLE door closed in each affected air lock within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 3.
Operation may then continue provided that an OPERABLE door in each affected air lock is maintained closed and is verified to be locked closed at least once per 31 days, and provided that the containment air lock passes each scheduled t
performance of SR 4.6.1.3b.
4.
Otherwise, be in 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 />, i
- b. With one or more containment air locks inoperable except as a result of an inoperable air lock door or air lock interlock mechanism:
1.
Verify at least one door in each affected air lock is closed within
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one hour, and 2.
Restore air lock (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
Otherwise, be in HOT STAN0BY 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 />.
- Entry and exit through the OPERABLE door is permissible if necessary to perform repairs of the affected air lock components. After each entry i
and exit, the OPERABLE door must be closed without delay.
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DAVIS-BESSE, UNIT 1 3/4 6-6 Amendment No.194 v-
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CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall ', demonstrated OPERABLE:
a.
By verifying either no detectable seal leakage when the volume between the door seals is pressurized to 10 psig, or by verifying a seal leakage rate of f 0.0015 L when the volume between the door seals is pressurized to P,, 38 psig, and the air lock door holddowns are installed:
- 1. #Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening, (in MODES 1, 2, 3 and 4) except when the air lock is being used for 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 />, and
- 2.
- Prior to establishing CONTA JMENT INTEGRITY when maintenance has not been performed on the air lock that could affect the air lock sealing capability.
Reperformance of this test is not required prior to entering MODE 4 if the air lock has not been i
opened since the previous test.
i b.
By conducting an overall air lock leakage test at P,, 38 psig, and by verifying that the overall air lock leakage rate is within its i
. limit:
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- l. #At least once per 6 months, and
- 2.
- Prior to esm blishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.
c.
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
f I
- Exemption to Appendix "J" of 10 CFR 50.
- The provisions of Specification 4.0.2 are not applicable.
l DAVIS-BESSE, UNIT 1 3/4 6-6a Amendment No.194 i
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3/4.6 CONTAINMENT SYSTEMS BASES m
3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from t*ne containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.
This restriction, in conjunction with the leakage rate limitation and air lock door requirements, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure of 38 psig, P As an added conservatism, the measured overall integrated leakage,. rate is further limited to 5 0.75 L, during performance of the periodic tests to account for possible deg,radation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent 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 when the plant is shutdown for the 10-year plant inservice inspections.
The operational readiness of the vessel is considered proven by the ILRT, i
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 seats. The special test is performed in addition to the Appendix J requirements.
USAR 6.2.4 identifies all penetrations that are secondary containment bypass leakage paths.
3/4.6.1.3 CONTAINMENT AIR LOCKS 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 provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
DAVIS-BESSE, UNIT 1 B 3/4 6-1 Amendment No. M,JM,A6S,194
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