ML19290A379
| ML19290A379 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/21/1975 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A380 | List: |
| References | |
| NUDOCS 7911060618 | |
| Download: ML19290A379 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSiOfJ W ASHING ton. D.
C.
20555 METROPOLITAN EDISON CO*!PANY JERSEY ClNIR\\L PUhlR A.ND LI6iff CGMPLY PE'uSYLVANIA LLECTRIC CO.' IPA.Y N
DOCKET NO. 50-2S9 DiREE MILE ISL.\\';D NUCLEAR STATION, UNIT 1 AMENTriENT TO FACILI'lY OPERATING LIENSE Amendment No. 5 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Commission) having found that:
A.
The application for amendment by Metropolitan Edison Comnany, Jersey Central Pcwer and Light Company, Pennsylvania diectric Ccmpany (the licensces) dated December 13, 1974, cc:rplies,ith 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; P,. The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Viere is reasonabic 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 Comission's regulations; D.
The 3.ssuance of this amendment will not be inimical to the cc=cn defense and security or to the health and safety of the public; and E.
Prior public notice of this anendment is not required since the amendment does not involve a significant hazards consideration.
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Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.c. (2) of Facility License No. DPR-50 is hereby amended to read as follows:
"(2) Technical Snecifications Tne Technical Specifications contained in Appendices A and 11, as revised are hereby incorporated in the license.
The licensees shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 5" 3.
'Ihis license amendment is effective as of the date of its issuance.
FOR TIE NUCLEAR REGULATORY CO:4 FISSION Karl R. Goller, Assistant Director for Operating Reactors Di"ision of Reactor Licensing
Attachment:
Change No. S to the Technical Specifications Date of Issuance: M 2 1 1975 1556 238 f
ATTAONENT 10 LICENSE AMEND!EST NO. 5 ORNGE NO. 510 'IHE TEGNICAL SPECIFICATI0N, FACILITY OPERATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace pages 3-3, 3-4, and 3-5 with the attached revised pages.
Replace page 3-6 with the attached page (no change was made therein but is being replaced for nurnbering sequence only). Also, replace Figures e
3.1-1 and 3.1-2 with the attached revised figures.
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.AoSlicebility e-Applies to pressurination, hea cp, and coc1down of the reactor cool 2nt systet.
Obiective syste.n do To assure that temperature and pressure changes in the reactor coolant syste.. components.
cause cyclic leads in excess of design for reactor coolant not Srecification 3 1.2.1 For the first 1.7 x 10 thermal negawatt days (approximatins,tvo pressure and the systen heatup and years) the rea:ter c:clant cooldown rates (with the exception cf the pressurizer) shall be limited in 20 ordance with Figure 3.1-1 and Ficure 3.1-2 and are as follows:
Heatup:
to the Allovable cenbinations of pressure and tenperature shall be right of and belev the limit line in Figure 3.1-1.
Hestup rates shall not exceed those shown on Figure 3.1-1.
Cooldown:
Allevable c:nbinations of pressure and tenperature for a specific line in cooldown shall be to the left of and below the limit Figure 3.1-2.
Cooldown rates shall not exceed these shovr on Figure 3.1-2.
Hydro Te::.
For isothermal systen hydrotests during the first two years cf set fort" operations t?.e s.yste nay be pressurized to the lir:it:
vesr el in Specification 2.2, when there are fuel assenblies in th.:
and to A5.'Z Ocde Section III limits when no fuel assenblics are Yr.e sys en present if -he systen tenperature is 215 F or greater.
may be tested to a pressure of 1150 u.si c.rovided syste
- a-~. '-a cr2 6
Initial systen hydrotesta prior to cr'ticalit; is 175 F cr greater.
=ay be conducted if the reacter coolant systc= temperature is 115 7 cr greater.
The secondar/ side of the steam generator shall not be pres..cri ed 3 1.2.2 tf the temperature of the _ steam generater chell in above 200 psie-below 100 F.
eneced 1000F it.
5 3.1.2.3 The pressurizer heatup and cocidown shall not l
any One h:cr. The spray shall net te used if the tenre-a--
~,
difference between the pressarizer and the spray fluid is creater than h3CF.
Within two ye rs of power operation, Figures 3.1-1 and 3.1-2 she.11 3.1.2.L he updated ir accordance with criteria acceptable to the ALC.
1556 240 esses syste. cenpenents are de:i ned to withstand the effects of All reneter coolant cyclic loads due to systen te.perature and pressare chances.ll)
These cyclic
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Tne pressure limit line en Figne 3.1-1 has been selected such that the reactor vessel stress resiting frc: internal pressure vill not exceed 15 percent yield str;ngth censidering the following:
e.
A 25 psi error in ceasured pressre b.
Syste= pressure i =easured in either loop c.
Maxit= differentie.1 press =e betveen the point of syste press.ure measre:ent and reac:cr vessel inlet fer all operating pump combinations For adequate conservatis=, in lieu ci portions cf the Fracture Toughness Test:. g ?.es.irinents cf the : ::: sed A::eni /. G :o 10. CFR 50, a taximun pressure of 550 psig e.d a nExik
-a':hp rate cf 50 y in any one hc= has l5 been imposed belev 275, F as shewn cn Figure 3.1-1.
The spray te perature difference restricticn, based on a stress entlysis of the sprcy line no::le is inposed to 221..tain the thernal stresses at the pressu -izer spray line no::le ':elev he design licit. Te perature require-ments for the stea= genera:Or corresp nd vith the =casured HLTT for the shell.
Er e...r.,_r.m.
a-(1)
FSAR, Section 1. 1.2.h (2)
.AS:G Boiler er.d Pressure Code,Section III, N kl5 (3)
FSAR, Sectice L.3.10 5 (h)
FSAR, Section b.3.3 (5)
FSAR, Section L.L.5 (6)
FSAR, Sections L.1.2.o a.d L.3.3 1556 241 P00R ORGIUL e
3-5 e
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.' POINT TEMP.
PRESS.
A 40 550
<B 275 550 C
275 1400 2400 0
380 2275
-0 2200 2000 E.
1800 S
5 y
1600
- UPPER PRESSURIZAT!CN 1400 C
I r
Z E
1200
_a_
8 1000 B
UPPER 000 PRESSURIZATION,
LlHIT E
3_
600
_E.
B 400 5
liAXINUM HEATUP F in any ene
. hour 200 50 100
=
0 0
100 200 300 400 500 275 Indicated R actor Coolant System Temperature.'F 1556 242 P.EACTOR CCOLAMT SYSTEM HE ATUP LlMIT AT 0:;S (APPLICABLE UP TO AN INTEGRATED E.iPCIURS G.:
1.7 x 10 13 sjcv.2 02 DTT : 154 F )
TilREE MILE ISLLND NUCLEAR STATION L?i!T !
FIGUR E 3.1-1 l
/
.' POINT TEMP.
PRESS.
A 40 550
<B 275 550 C
275 1400 2400 _
0 380 2275
-0 2200 2000 8.
1800 S
5 y
1600
- UPPER PRESSURIZATICN
[j 1400 C
w E
1200 8
1000 S
VPPER
[
PRESSURIZATICN,
800 LlHIT
=
3 600 I
400 5
MAXINUM HEATUP F in any ene
, hour 200 50 100 l
I I
I 0
O 100 200 300 400 500 215
~
Indicat:d Reactor Ccolant Systen Temperature.'F 1556 243 P.E/.CTOR COOLAMT SYSTE.'A HE ATUP LlMIT ATIONS (APPLICABLE UP TO AN INTEGR ATED E."P05URE G.:
1.7 x 10 3 H /C.V.2 02 DTT : 154 F )
1 T11REE MILE 15LeiD NUCLEAR STATION L?i!T I FIGUR E 3.1-1 l
.