ML20154D678
| ML20154D678 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/01/1988 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 1583, TAC-66753, NUDOCS 8809160051 | |
| Download: ML20154D678 (6) | |
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4 TOLE 00
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DoNAto C. SHEtTON
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Docket No. 50-346 1
License No. NPF-3 Serial No. 1583 September 1, 1988 l
1 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.
20555 Subj ec t: License Amendment Application Change Pages Regarding Referencing of the Control Rod Position Svitches for Remote Shutdovn Instrumentation (TAC No. 66735) l I
Centlemen
(
By letter dated August 5, 1988 (Serial No. 1492), Toledo Edison submitted an application for an amendment to the Davis-Besse Nuclear Pover Station, Unit No. 1 Operating License, Appendix A. Technical Specifications involving Section 3/4.3.3.5, Instrumentation, Remote Shutdovn Instrumentation. Tables 3.3-9 and 4.3-6.
That submittal inadvertently omitted the marked-up Technical Specification pages depicting the requested changes.
Enclosed are those l
marked-up pages which complete the License Amendment Application as previously transmitted by the aforementioned letter.
't you have any questions, please contact Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-2366.
Very truly yours,
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Attachment cci DB-1 NRC Resident Inspector l
A. B. Davis, Regional Administrator (2 copies)
State of Ohio A. V. DeAgazio, NRR Davis-Besse Project Manager
[KOI 8809160051 880901 l
PDR ADOCK 05000346 l
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Docket Nq. 50-346 Lic'ense No. NPF-3 L. p p g t,,T 1l" h,
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Attachment i
Page 1 of 5 INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring ir,5trumentation channels shown in Table 3.3 9 shall be OPERABLE with readouts displayed external to the control rcom.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
3.
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 />, b.
The provisions of Specification 3.0.4 are not applicable.
SURVE!LLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown rronitoring instrumentation channel shall be demonstrated OPERABLE by performance of tne CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4,3 6, DAVIS-BESSE, UNIT 1 3/4 3-43
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RDIOTE SMUTDOWN MONITORINC IIRSTRIDGENTATION
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MINIMUM atANuff MEASUREMENT ruammert t INSTRIBfENT LOCAT1001 RANCE OPraamt r N
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Reactor Trip Breaker Indicaties (a) 480,F6DC CE. 2.
OPEN-CLOSE (a) 1 (Trip Breaker A)
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Switchgear Room (b) 480v E&DC CII. 1 (b) 1 (Trip Breaker B)
Switchgear Room (c) 490v F&DC CII. 2 (c) 1 (Trip Breaker C)
Switchgear Room u
(d) CRDC Cabinet Room (d) I (Trip Breaker D)
N 2.
Reacter Coelant Temperature - Not Leg Aux. Shutdown Fanel 520-620 *r I
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3.
Reactor Coelant System Pressure Aux. Shutdown Fanel 0-3000 peig I
4.
Pressuriser Level Aux. Shutdown Fanel 0-320 inches 1
5.
Steam Ceeerster outlet Steam Pressure Aux. Shutdown Fanel 0-1200 peig I/ steam senerator 6.
Steen Generator Level Startup Range Aux. Shutdown Fanel 0-250 inches I/eteam generator 7.
Control Red Fasition,Meee Switches Centrol Red Drive 0, 25, 50, 75 I/ red Centrol Cabinete, and 3001 System Logic Cabinet #4 n
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Rosit Siml00bal MONIi_ni_t_I_N_G_. _I_NSIM8ENTAll0N SMRWll1 AfeCE REQUINfENIS y
CHAIGEL CHAINEL INSIMBENT OIECK CALIBRAIIGIl a
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Reacter Trip Breaker Indication M
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2.
Reacter Coolant Temperature-Mot legs M
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3.
Reacter Caelant ijstem Pressure M
R 4.
Pressurizer level M
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Steam Generator Outlet Steam Pressure M
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Steam Generator Startup Range level M
R 7.
Centrol Red Position SwitcInes M
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' Docket No. 50-346 Lictn o b'o. NPF-3
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THIS PAGE PNilDED Pags 4 of 5 3/4.3 INSTRUMENTATICN BASES t
3/4.3.3 MON!TORING INSTRUMENTATION 3/4.3.3.1 RADI ATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that
- 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or aut:catic action is initiated when the radiation level trip setpoint is exceeded.
4 3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectcrs ensures that the measurements obtained from use of this system accurately represent the spattal neutron flux distribution of the reactor core.
See Bases Figures 3 1 and 3-2 for examples of acceptable minimum incore detector arrangemeats.
3/4.3.3.3 SE!SMIC !NSTRUMENTATION J'
The OPERABILITY of the seismic instrumentation ensures that suff t-cient capability is available to promptly detemine the magnitude of a seismic event so that the response of those features important to safety may be evaluated.
This capability is required to permit comparison of the measured response to that used in the design basis for the factitty.
This instrumentation is consistent with the recomendations of Regulatory Guide 1.12 "Instrumentation for Earthquakesd April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the pubite as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for inttfating protective measuras to protect the health and safety of the pubite. This instrumentation is consistant with the recomendations of Re Meteorological Programs," February 1972. gulatory Guide 1.23 "Cnsite i
3/4.3.3.5 REMOTE SHUTDCWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrtantation ensures that j
sufficient capabiltty is available to permit shutdown and maintenance of DAVIS-BESSE, UNIT 1 8 3/4 3-2
~ Doc'k$tNo. 50-346 Lictnee $o. NPF-3
=-
HIS~PAGE PROVIDED Page 5 of 5 3/4.3 INSTRUMENTATION BASES REMOTE SHUTDOWN INSTRUMENTATION (Continued).
HOT STANOBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost.
3/4:3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that suffi-cient information is available on selected plant parameters to monitor and assess these variables following an accident.
3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that an acci-dental chlorine release will be detected promptly and the control room emergency ventilation system will automatically isolate the control room and initiate its operation in the recircC ation mode to provide the required protection. The chlorine deter.on systems required by this specification are consistent with the res wsnendations of Regulatory Guide 1.95 "Protection of Nuclear Power.1 ant Control Room Operations Against an Accidental Chlorine Release " February 1975.
I
, DAVIS-BESSE, UNIT 1 8 3/4 3-3