ML20069N641
| ML20069N641 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/14/1994 |
| From: | West G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069N644 | List: |
| References | |
| NUDOCS 9406230086 | |
| Download: ML20069N641 (9) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINoToN, D.C. 20666-0001
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TOLEDO EDISON COMPANY j
CENTERIOR SERVICE COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison. Company, Centerior Service Company, and the Cleveland Electric Illuminating Company i
(the licensees) dated December 23, 1992, as supplemented on March 18, I
1994, complies with the standards and requirements of the Atomic l
Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and. regulations of the l
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; i
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 i
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:
l 9406230006 940614 l
l PDR ADOCK 05000346 P
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(a) Technical Soecifications~
The Technical Specifications contained in Appendix A, as revised through Amendment No.187, are hereby incorporated in the license, l
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 startup from the first refueling outage after approval of this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Garmon West, Jr., Acting Project Manager Project Directorate III-3 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
June 14, 1994
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l ATTACHMENT TO LICENSE AMENDMENT N0. 187 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET N0. 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.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 3-43 3/4 3-43 8~3/4 3-3 8 3/4 3-3 6-18 6-18
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INSTRUMENTATION REMOTE SHUTOOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The remote shutdown monitorina instrumentation channels shown in I
Table 3.3-9 shall be OPERABLE with readcats displayed external to the control room.
3.3.3.5.2 The control circuits and transfer switches required for a serious control room or cable spreading room fire shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
l ACTION:
a.
With the number of OPERABLE remote shutdown monitoring channels less
['
than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i b.
With one or more control circuits or transfer switches required for a i
j serious control room or cable spreading room fire inoperable, restore the inoperable circuit (s) or switch (es) to OPERABLE status within 30 i
days, or prepare and submit a Special Report to the Commission
,1 pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the circuit (s) or switch (es) to OPERABLE I
status.
c.
The provisions of Specification 3.0.4 are not applicable.
i lSURVElLLANCEREQUIREMENTS i
i
' 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be l
demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL 1
CALIBRATION operations at the frequencies shown in Table 4.3-6.
4.3.3.5.2 At least once per 18 months, verify each control circuit and transfer switch required for a serious control room or cable spreading room fire is capable of performing the intended function.
l 4
DAVIS-BESSE, UNIT 1 3/4 3-43 Amendmer: No.187 8
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TABI.E 't.1-9 N
_RFMOTE SilliTDOWN MONITORI NG I NSTRiiM ENTAT'ON E
TA w
MINIMifM READollT HEASlfREMENT CIIANNEl.S INSTRUMENT I.0 CATION RANGE OPERAn!.E 1.
Reactor Trip Breaker Indication (a) 480v FADC CH. 2 OPEN-CLOSE (a) 1 (Trip Breaker A)
Switchgear Room (b) 480v EADC CH. 1 (h) 1 (Trip Breaker B)
Switchgear Room (c) 480v F&DC CH. 2 (c) 1 (Trip Breaker C)
Switch ear Room R
w (d) CRDC Cabinet Room (d) 1 (Trip Breaker D)
N 2.
Reactor Coolant Temperature - Hot leg Aux. Shutdown Panel 520-620 *F 1
w L
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3.
Reactor Coolant System Prennure Aux. Shutdown Panel 0-3000 psig 1
4 Pressurizer Level Aux. Shutdown Panel 0-320 inches 1
5.
Steam Generator Outlet Steam Pressure Aux. Shutdown Panel 0-1200 psig 1/ steam generator 6.
Stese Generator Level Startup Range Aux. Shutdown Panel 0-250 inches 1/ steam generator 7.
Control Rod Position Switches Control Rod Drive 0, 25, 50, 75 1/ rod Control Cabinets.
and 100%
C System Logic d
Cabinet #4 5
5 M
M LJ1 9
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7 3/4.3 INSTRUMERTATION l
BASES 1
REMOTE SHUTOOWN INSTRUMENTATION (Continued)
HOT STANDBY of the f acility from locations outside of the control room.
This l
capability is required in the event control room habitability is lost.
SR 4.3.3.5.2 verifies that each Remote Shutdown System transfer switch and control circuit required for a serious control room or cable spreading room fire performs its intended function.
This verification is performed from the remote shutdown panel and locally, as appropriate.
This will ensure that if the control room becomes inaccessible, the unit can be safely shutdown from the remote shutdown panel and the local control stations, i
l 3/4.3.3.6 POST-AtCIDENT MONITORING INSTRUMENTATION l
i
! The OPERABILITY of the post-accident monitoring instrumentation ensures that
! sufficient information is available on selected plant parameters to monitor i and assess these variables following an accident.
The containment Hydrogen Analyzers, although they are considered part of the plant post-accident g
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l} monitoring instrumentation, have their OPERABILITY requirements located in i Specification 3/4.6.4.1, Hydrogen Analyzers.
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' 3/4.3.3.7 CHLORINE DETECTION SYSTEMS - Deleted i 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION - Deleted I
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DAVIS-BESSE, UNIT 1 B 3/4 3-3 Amendment No.9,50,52,734, 15E,1E7,179,167
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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 50.4 within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications:
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
a.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
- c. ' Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
e.
Deleted f.
Deleted Inoperable Remote Shutdown System control circuit s 9
switch (es) required for a serious control room or(ca)ble spreading or transfer room fire, Specification 3.3.3.5.2.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
Records and logs of facility operation covering time interval at each a.
power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to Operating Procedures, e.
f.
Records of radioactive shipments.
Records of sealed source and fission detector leak tests and results.
g.
h.
Records of annual physical inventory of all sealed source material of record.
- DAVIS-BESSE, UNIT 1 6-18 Amendment No. 9,12.65.86, 106,135,110,1 H 187
a ADMINISTRATIVE CONTROLS The following records shall be retained for the duration of the 6.10.2 Facility Operating License:
Records and drawing changes reflecting facility design modifica-tions made to systems and equipment described in the Final Safety.
a.
Analysis Report.
Records of new and irradiated fuel inventory, fuel transfers and b.
assembly burnup histories.
Records of radiation exposure for all individuals entering radiation c.
control areas.
Records of gaseous and liquid radioactive material released to the d.
environs.
Records of transient of operational cycles for those facility e.
components identified in Table 5.7-1.
f.
Records of reactor tests and experiments, f '.
Records of training and qualification for current members of the I;
g.
ll plant staff.
Records of in-service inspections performed pursuant to these ll:.
h.
Technical Specifications.
Records of Quality Assurance activities required by the QA Manual.
i.
Ii Records of reviews performed for changes made to procedures or equip-j.
ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
l k.
Records of meetings of the SRB and the CNRB.
Records for Environmental Qualification which are covered under the 1.
provisions of paragraph 6.13.
Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of m.
the analyses at a later date. This should include procedures.
effective at specified times and QA ~ records showing that these procedures were followed.
Records of the service lives of all safety related hydraulic and mechanical snubbers including the date at which the service life o.
commences and associated installation and maintenance records.
Records of reviews performed for changes made to the OFFSITE DOSE p.
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
Amendment No. 5,JZ,86,H.170 l 6-19 DAVIS-BESSE, UNIT 1 Order dated Oct. 24, 1980
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