ML20245F574

Amend 134 to License NPF-3,deleting Sections 3/4.3.3.7, Chlorine Detection Sys from App a & 3/4.3.3.7 from Bases

ML20245F574
Person / Time
Site:	Davis Besse
Issue date:	08/04/1989
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245F578	List: ML20245F574 ML20245F579
References
NUDOCS 8908140418
Download: ML20245F574 (9)

Text

-

pf UNITED STATES

• g y r (,g NUCLEAR REGULATORY COMMISSION j.jp p WASHINGTON, D. C. 20555

.....f A

TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 License No. NPF-3 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated January 15, 1988 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 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conuutted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comissior's regulations; D.

The issuance of this amendment will not be inimical to the comen 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 Pcrt 51 of the Comission'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:

P l

1 !:

(a) T~echnical Specifications The Technical Specifications contained in Appendix A, as revised through Amenenent No.134, are hereby incorporated in the license.

The Toledo E< ison Company shall operate the facility in accordance with the Teci r.icel Specifications.

3.

This 11centc. onendment is effective as of its date of issuance and shall be imp %ented not later than September 18, 1989.

l FOR THE NUCLEAR REGULATORY COMMISSION 4

4D**

~

John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nucle =.r Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 4, 1989

~

ATTACHMENT TO LICENSE AMENDMENT NO.134 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following acges of the Appendix "A" Technical Specifications with the attached pages. T1e 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 IV IV 3/4 3-51 3/4 3-51 B3/4 3-3 B3/4 3-3

___m_. _ _ _ _ _ _ _ _ _ _ _ _.. _ _ _ - _ - _... - -

n.

)

INDEX l

i UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS.

I SECTION f1G,E 3 /4. 0 APPU CABIUTC..........................................

3/40-1 3 /4.1 RE. ACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR01.

~ '

Sh u t down Ma rg in...................................... 3/4 1-1 B o ro n D i l u'L i on.............'. u...'............ -....... 3/4 1-3 Mode ra tor Te=p e ra ture Co ef fi c ient.................... 3/41-4

~

Hinimum Tempe ra ture for Cri tica l i ty.................. 3/4 1-5

't/4.1.2 BORATION SYSTD'.S Fl ow Pa ths - 3hutd own................................ 3/4 1-6 Fl o w P a'ths - Op e r a t i n g............................... 3/4 1-7 Ma cu p Pump - 5hu tdown............................*.. '

3/4 1-9 Ma k eup fumps - Opera ti ng.............................

3/4 1-10 Decay Heat Ramoval Pump - Shutdown................... 3/4 1-11 Boric Acid Pump - 3hutdown...........................

J/4 1-12'

~

Be ric Ac id Pumps - Opera ting......................... 3/4 1-13 Be ra ted Wa ter Sources - Shutdown..................... 3/4 1-14

~

Bera ted Wa ter Sources - Opera ting.............,.......

3/4 1-17 3/4.1.3 MOVASLE CONTROL ASSEMBLIES Group Height Safety and Regulating Rod Grou;:s......

3/4 1-19 Group Height - Axial Powe-Shaping Rod Grcup.........

'l/4 1-Zi; Po si tion Indica tor Channel s.......................... 3/4 h 22 Rod Drop Time..............................'..........

3/4 1-24 Sa fe ty Re d Ins ertion Limit...........................- 3/4 1-25 Regula ting Red Ins ertion Limits.....................S 3/4 1-26 Re d P ro gram..........................................

3/4 1-30 Xenon, Reactivity.....................................

3/4 1-33

. Axial hwer Shaping Rod Insertion Limits...............

3/4 1-34 l

n

,; DAYIS-BESiE. UNIT 1

.III Amendment No. 38

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POVER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POVER IMBALANCE.................

3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX BOT CHANNEL FACTOR - F0.......

3/4 2-5 N

3/4.2.3 NUCLEAR ENTHALPY RISE BOT CHANNEL FACTOR - Fg.....

3/4 2-7 3/4.2.4 OUADRANT POVER TILT..................

3/4 2-9 3/4.2.5 DNB PARAMETERS.....................

3/4 2-13 3/4.3 INSTRUME! CATION 3/4.3.1 REACTOR PROTECTION SY$ TEM INSTRUMENTATION.......

3/4 3-1 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION Safety Features Actuation System............

3/4 3-9 Steam and Feedvater Rupture Control System......

3/4 3-23 Anticipatory Reactor Trip System............

3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation..........

3/4 3-31 Incore Detectors....................

3/4 3-35 Seismic Instrumentation................

3/4 3-37 Meteorological Instrumentation.............

3/4 3-40 Remote Shutdown Instrumentation............

3/4 3-43 Post-Accident Instrumentation.............

3/4 3-46 I

Fire Detection Instrumentation.............

3/4 3-52 Radioactive Liquid Effluent Monitoring Instrumentation.

3/4 3-57 Radioactive Gaseous Effluent Monitoring Instrumentation. 3/4 3-62 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............

3/4 4-1 Shutdown and Hot Standby................

3/4 4-2 3/4.4.2 SAFETY VALVES - SHUTDOWN................

3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -

OPERATING......................

3/4 4-4 DAVIS-BESSE, UNIT 1 IV Amendment No. 38, /ty,134

l t

l.

INSTRUMENTATION CHLORINE DETECTION SYSTEMS DELETED DAVIS-BESSE, UNIT 1 3/4 3-51 Amendment No. 134

i INSTRUMENTATION

_? IRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 detection zone shown in Table 3.3-14 shall be OPERA 3 L L

APPLICABILITY:

Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION:

the minir.un number OPERA 3LE requirement of Table 3.

s ess than Within I hour establish a fire watch patrol to inspect th a.

accessible sene(s) with the inoperable instrument (s) at least e

ence per hour, and-b.

Restore the inoperable instrument (s) to CPERABLE status withi 14 days or prepare and submit a Special Report to the Commissio n

the action taken, the cause.of the inoperability an

~

and schedule for restoring the instrument (s) to OPERABLE status.

The provisions of specifications 3.0.3 and 3.0.4 are not c.

applicable.

S N EILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required accessible fire detection instruments shall be demonstrated CPERA3LE at least once per 6 months by performance of a CF.ANNEL TUNCTICNAL TEST.

Each of the above required inaccessible fire detection instruzent shall be demonstrated OPERAELE at least once per 18 senths by performance of a CHANNEL FUNCTIONAL TEST.

4.3.3.8.2 The hTPA Code 72D C1ssa A supe sed e r u ts a pe k

sssociated with the detec or ala s

e ira detection instruments s d

6 months.

onstrated CPERAILE at least once per 4.3.3.8.3 The non-supervised circuits between the local panels in Specification 4.3.3.8.3 and the control room shall be demonstrated l

OPIRABLE at least once per 31 days.

i DAVIS-SESSE. UNIT 1 3/4 3-52 i

Amendment No. M )4 93 e

I

3/4.3 INSTRUMENTATION j

BASES l

l REMOTE SHUTDOWN INSTRUMENTATION (Continued)

HOT STANDBY 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 IN5TRUMENTATION 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 - Deleted 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION,

0perability of the fire detection instrumentation ensures that adequate

' warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall' facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provile detection capability until the inoperable instrumentation is restored to OPERABILITY.

DAVIS-BESSE, UNIT 1 B 3/4 3-3 Amendment No. 9,50,E8,134

o

(

W:-

gg essa.mm

====.m a"* M TRY

[

.s> 8 f " f - % > c' l

TOP m &LCDAS "s

man N'

/

g c

Q r

=

I

/-

~%

o g

y l

f

\\

i t...:j O

M a& PLANS

\\ s s

\\

=======.

.ms.-=*

Ig.

r-

===m> %

N

==

.[

\\

SOTTOGA AAtak Cent

(

/

Mak8 g.

/

s

, * * * * * * * ~ " ' " ' ' ' ' ~,

/

s

/

S J

j Bases F'gwre 31 Incore Instrumentation Soscificenen Acceptante Minimian AXIAL POWER lMBALANCE Arregenent I

uAVIS-BESSE. UNIT 1 3 3/4 3-4 i

_a_

-