ML19254F188
| ML19254F188 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/15/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18044A203 | List: |
| References | |
| NUDOCS 7911070291 | |
| Download: ML19254F188 (12) | |
Text
.
[ v at%9 UNITED STATES NUCLEAR REGULATORY COMMIS' N
WASHINGTON D. C. 20555 S
%,.....,o CONSUMERS P014ER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO DR0lISIONAL OPEP.ATING LICENSE Amendment No. 53 License No. DPR-20 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Censumers Power Company (the licensee) dated June 13, 1978, as revised by letter dated March 6, 1979, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chaoter I:
B.
The facility will operate in confonnity with the application, the orovisions 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 reaulations; 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 reouirements have been satisfied.
1289 00' 7911070
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment and paragraph 3.B of Provision Operating License No.
DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in An.endix c
A, as revised through Amendment No. 53; are hereby incorporated in the license.
The itcensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
<,,,_ /s L.m.-
y
~
Dennis L. Ziemanry Chief Operating Reactors Branch #2 Division of Operating Reactors Attachnent:
C'hanges to the iechnical Specifications Date of Issuance:
October 15, 1979 1289 T
ATTACHMENT TO LICENSE AMENDMENT NO. 53 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A by removing the following pages and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of chance.
PAGES 11 4-16 4-17 4-18 4-19 4-20 4-21 4-22 4-45 1289 00'
TABLE OF CONTENTS (Coutd)
Descriction
,s.fjt Sectien LIICInG CO3DITIONS FOR OPIPATICH (Conti' 30 3-58 3 10 Centrol P.od e=d Power Distribution Li=its 3-58 3 10.1 Shutdo en Margin Require =ents 3-58 3 10.2 Individual Red Worth 3-59 3 10.3 Power Distribution Limits 3 10.h Misaligned or Inoperable control Rod or Part-Length 3-59 Rod 3-60 3 10.5 Regulating Group Insertion lim ts 3-00 3.10.6 Shutdown Rod Limits 3-60 3 10.7 Lov Pover Physics Testing 3-65 3 11 In-core Instrumentation 3-67 3 12 Moderator Te=persture Coefficient of Reactivity 3 13 Contair-ent Building r.nd Fuel Storage Building Crar.es 3-69 3-70 3 1h Control Roo= Air Te=perature 3-TC 3 15 Reactor Prir.ary Shield Cooling Syste 3.16 Engineered Safety Features Syste= Initiation Instru-3-71 mentation Settings 3-76 3 17 Instrumentation and Control Syste=s 3-82 3 18 secondary */a er Chemistry 3.19 Linear Ecac Ceneration Rate f'-dts Associated With 3-Sh IECA Considerstions 3-88 3.20 Shock Suppressors (Snubbers)
Move =ent of Heavy Loads Over the Spent Fuel Fool (To 3 21 3-92 Be Subnitted) 3-96 3.22 Fire Protection Syster.
3-96 3.22.1 Fire Detection Instru=entation 3-98 3 22.2 Fire Suppression Water Syste=
3-100 3 22.3 Fire Spr Ne'er Syste 3-101 3.22.k Fire Hose Stations 3 22.5 Penetration Fire Barriers 3-102 h-1 h.O SURVEILLANCE REQUIREMENTS h-1 h.1 Instru=entation and C6=tror h-13 k.2 Equipment and Sa=pling Tests h-16 h.3 Systems survet' lance' k-24 4.h Primary Coolazrc Syste= Integrity Testing h-25 k.5 Contain=ent Tests h-39 h.6 Safety Injectics and Contain=ent Spray Syste=s Tests k h2 h.7 Energency Power System Periodie-Tests h La h.8 Main Stes= Stop Valves h h5 h.9 Auxiliary Feed-Water Syste=
h h6 k.10 Reactivity Anonalies M7 k.11 Environ = ental Monitoring Prog e=
1289 P 11 Amendment No.fif, 53
h.3 SYSTD'S ELTvEILLA' ICE APPLICA3ILITY Applies to preoperational and inservice structural surveillance of the reacter vessel and other Class 1, Class 2 and Class 3 system cceponents.
C3JECTIVE To insure the integrity of the Class 1, Class 2 and Class 3 piping systems and cc=ponents.
SPECIFICATIONS a.
Prior to initial plant cperation, an ultrasonic survey shall be made of reac r vessel shell velds, vessel nozzles, vessel flange velds, piping,ystem butt velds and major velds on the pressurizer and steam generators to establish preoperational system integrity and basic conditions for future testing.
L.
The structural integrity of ASME Class 1, 2 and 3 cc:ponents, as determined by 10 CFR 50, Section 50 55a and Reg Guide 1.26, shall be verified and maintained at an acceptable' level in accordance with Section XI cf the ASME B&FV Code with appliceble addenda as required by 10 CFR 50, Section 50.55a(g), except where specific relief has been granted by the NRC, and where provisiens of Section k.12 take precedence.
Inservice testing of ASME Class 1, 2 and 3 pu=ps, as c.
deter =ined by 10 CFR 50, Sectica 50 55a and Reg Guide 1.26 shall be perfer=ed in accordance with Section XI of the ASME B&PV Code with applicable addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific relief has been granted by the NRC.
4.
Sufficient records of each inspection shall be kept to allow co= pari-sen and evaluation of future tests.
The Inservice Inspection progrs= shall be reevaluated as required by e.
10 CFR 50, Section 50 55a(g)(5) to censider incorreration of new l289 0o' h-16 Amendment No. 53
inspection technioues that have been proven practical, and the conclu-siens of the evaluation shall be used as appropriate to update the inspection program.
f.
Surveillance of the regenerative heat exchanger and pri=ary coolant pu=p flywheels shall be perfor=ed as indicated in Table h.3.2.
g.
A surveillance progra to monitor radiation induced changes in the
=echanical and i= pact properties of the reacter vessel =aterials shall be maintained as described in Section 4.5.3 cf the FSAR. The specimen re= oval schedule shall be as indicated in Tatie h.3.3.
EASIS The inspection program specified places =e.jor emphasis on the areas of highest stress concentration as deter =ined by general design evaluation and experience with sLnilar syste=s.
In addition, that portien of the reactor vessel shell velds which vill be subjected to a fast neutron dose sufficient to change ductility properties will be inspected.
The inspec-tions vill rely primarily en ultrasonic methods. utilizing up-to-date ana-lyzing equip =ent and trained personnel. Precperational inspecticns vill establish base conditiens by determining indications that =ight occur frc=
gec=etrical or metallurgical sources and frc= discontinuities in veld =ents or plates which =ight cause undue concern on a postservice inspection. To the extent applicable, based upon the existing design and construction of the plant, the require =ents of Section XI of the Code shall be cc= plied with.
Significant exceptions are detailed in the requests for relief which have received NRC approval and are contained in the Class 1, Class 2 and Class 3 Long-Ter= Inspection Plans.
REACTOR VESSEL SURVEILLANCE SPECIMENS Table k.3.3 is consistent with the surveillance program as presented in the FSAR.
However, the withdraval schedule has been =odified to re-flect the slightly different vall fluence values resulting frc= re= oval cf the ther=al shield.
REFERENCES (1) FSAR, Section h.5.o.
ggq (2) FSAR, Section h.5.3 h-17 Amendment No. 53
TABLE h.3.1 (Delete) 1289 'C' h-18 Amendment No. 53
o (INTENTIONALLY LErr 3mg) 1289 'C' 4-19 Amendment No. 53
(INTENTICNALLY LEFT BLANK) 1289
~C' h-20 Amendment No. 53
(INmiTIONALLY LEFT BLANK) 1289 'C' h-21 Aniendnient No 53 g
t (INTETIONALLY LEPT 3 LANK) 1289 :'?'
h-22 Amendment No. 53
49 AUXILIARY FEED-WATER SYSTDI APPLICABILITY Applies to periodic testing requirements of the turbine-driven and motor-driven auxiliary f eed-water pumps.
OBJECTIVE To verify the operability of the auxiliary feed-water system and its ability to respond properly when required.
SPECIFICATIONS The operability of the motor-and steam-driven auxiliary feed pumps a.
shall be confirmed as required by Specification 4.3c.
b.
The cperability of the auxiliary feed-water pumps' discharge valves CV-0736A and CV-0737A shall be confirmed at least every three (3) months.
BASIS The periodic testing of the auxiliary feed-water pumps vill verif y their operability by recirculating water to the condensate storage tank and si=ultaneously partially opening, one at a time, the discharge valves (CV-0736A and CV-0737A) to confirm a flev path to the steam genera-tors.
Proper functiening of the steam turbine ad=ission valve and the feed-vater pumps' start vill demonstrate the integrity of the stea=-driven micps.
Verification of correct operation vill be made both from instru-
~ +.
tr.ation within the rain control room and direct visual observation of
[
,h-
. umps.
~ UCES
'n o
'6 "O, [.
.... Section 9 7.
}'}@Q
'[]
- E
~'.h.'s y
a t
'C'3.t
~. :
.a.,
,s>
n,I[
4-45
. =;
'"'E -
Amendment No. 53 4
o
. -. -., _,..