ML19341C782
| ML19341C782 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/16/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341C775 | List: |
| References | |
| NUDOCS 8103040178 | |
| Download: ML19341C782 (6) | |
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g UNITED STATES ~
j-NUCLEAR REGULATORY COMMISSION y-e
': E W ASHINGTON, D. C. 20555
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CONSUMERS POWER COMPANY DOCKET N0. 50-155 4
BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated August 25, 1980, 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 appli-cation, 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 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.
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' 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.
DPR-6 is hereby amended to read as follows:
'(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 771 Dennis M. Crutchfield, Chi f Operating Reactors Branch #5 Division of Licensing i
Attachment:
Changes to the Technical Soecifications Date of Issuance: September 16, 1980 1
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 34 PROVISIONAL OPERATING LICENSE NO. DPR-6 DOCKET-NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identi-fied below and inserting the enclosed pages.
The revised pages contain o
the captioned amendment number and a vertical line indicating the area of change.
PAGES 6-2 11-3 li -9 (Table 3. 5.2. h)
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e 6.1.2 Heretor Surety Syste's During Power Operation w
e.
'Ihe following tabulation givea the arrangement, of the reactor safety system that shall be effective during power operation:
Trip Contacts Coincidence Scrum Uetting Warning Sensor und in Each in Euch und Ins t rumerit Annunciation Trip Device Channel Channel Tolerance special Features Ranges Trip Set Poisit High Reactor Pres-2 1 Out or 2 5015 Psi Above 100-1700 Psig 2515 Psi Above g
sure (Is Pressure Heuctor Oper-Reactor Operuting i
Switches) ating Pressure Pressure lg Lou Reactor Water 2
1 Out. or 2
> 2 ' 9" Above Closes containment Fixed Level 14 vel (16 Level Top or Active sphere isolut. ion Trip Point 1
Switches).
Vuel (Toler-vulves.
If reactor No Range g
unce1.{mit, pressure is less than
-1")
200 psig, actuat.es core spray system.
(Note: Spray water l
will not, enter reactor vessel until reactor g
pressure drops below fire header pressure.)
Above or Equal Imv Steum Drum 2
1 Out or 2
-30" to +30" li" below Steam to 8.0" Ilelow Water Level (l' Water Drum Center 1.ine Steam 1) ruin Level Swit.ches)
Center 1.ine h
(Tolerance i
Limit 1
-0. 5") (1) l Main Steam Line 2
1 Out or 2 5015 l'ercent or Ibsi t. ion Swi tch Backup Isolation Full Closure Trains Ad.lustable Valve Closure (Is Full Valve Travel Position Switches)
High Condenser 2
1 out or a 8.010.5" or lig Hypassed by pressure 0 - 30" lig vue Pressure (la Pres-Absolute Pres-interlock as describest sure Switches) sure i n Sec t, ion 6.1. ~1.
I Level instrument set point.s shull be as up.:cifierd.
I : vel instrwnent. calibration ahall be based on normal opernt.ine temperature (582"F) und pressure (1350 pain) und inut.rument. reference li,.g t.esperature or 250"F or Lover na mensur..I to maintain an actual trip level greater t han that assumed in accident unulyses (2'8" ubove t.op of active fuel for re act.er vessel level trips, and 38,500 Ihm inventory above active ruel for reactor protective system t. rip). Set point atri ct between calibration checks within the sin:eified tolerance limit. shall be correct.ed but, need not be reported unih:r
. Specifient. ion 6.9.2.
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TanIcu 3. '>.11.1.~
h. 5. 2. t Ins L rinnent.ut ion Tha t.
Ini ti ut es itIU 6e er, t.inti
- 3. 5.2.11 - I.imitint _ con _di t ions for operat ion le. 'i.2.li - Surveillance Requi rer.cnt.
Hiriimum l'rotective?
Opetuble Cond i t. ion.1 for
. Ins t. rumen t ins t.ru nent.
. Cl. anne t Pa rnme f.e r t'honnele I.imiting Met
- h. int n.ernbii!ty Tr i r. Tn. t. -
Ca t i bent. f on Tr i t.
r Low Steam. Drum 3
Above or logual to At.. Power I.
.il.
M.nthly Each thQor Level
.17" !!e low Cent er llhenever tme Refueling h
Line (Tolerarn e lienetor Is Limit -5")(lI Cr i t i. n1 ' :
t.
t.he lierad ( r.
r Wh.n in iL.t Shut down Fi re Pump (s )
>100 Palg Ditto
!brith ly Each Major Discharge Pressure lierueling t
Law Reactor 3
> 2 ' 9" A bov e T..p Menthly.
l<ach Major l
Water Level of Act.tve Fuel iterueling (Tolcrunce 1.imit i
-1")(1) s 120-Second 3
3120 Geconda Vol-Munthly.
Each Major Time Delay lowing low St crun Herueling Drum 1.evel Sir,nal Input Channels 3
Monthly A Through D 4
Output Channele 3
Nuthly I Through IV 1
" Fire Pwnp Start 1
Mont.bly mr.t.h ty 1
- Reference Specific ations 3.1.L un l 'h. J.h ror lb.uen.
(1) Level instriunent Let. [cintJ st. ! 1 Le. nt, spec i r t..d.
I.e ve l inu t riunent..d i b rat ion shall be bane 1 un norp.::1 1.m.it i ne.
temperature (502 F) and pressur e (1350 pula) and ins t rument. rereience 1-temperature or 2',o"V or low.:r as n.mu..r.:a t
to.maint,ain an uctm21 trip level greater than t hat. ansumed in accident nr.alysen (2'U" above t.op of act i ve r.el fo r reactor vessel level.tri[.a. an i 25" below steam drum cent.er line for !<.'d actuu t. ion ). Het poi n t, dri f t. be t w.: :n I
calibration checkc withir. the.pecified t.olerane'e Limit chull be corrwted but need not. be c; ported unter Specification (2 9.2.
1
'11-9 Amendmern No. l$, d. P1
.