ML19210B862
| ML19210B862 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/07/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210B863 | List: |
| References | |
| NUDOCS 7911120560 | |
| Download: ML19210B862 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION g
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WASHINGTON, D. C. 20666 e
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 38 License No. OPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (the licensees), dated February 17, 1978, as supplemented March 1,1978, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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50 P]M MEA _
i 2-2.
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-50 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 38, 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 the date of its issuance.
FOR THE NUCLEAR REGU ORY COMMISSION
,h 'Z'I Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1978 O
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.i ATTACHMENT TO LICEfiSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. OPR-50 i
DOCKET NO. 50-289 Revise Appendix A as follows:
Remove Pages Insert Paces vii vii 3-34a 3-34a j
3-35 3-35 3-35a 3-35a Fig. 3.5-2I Fig.23.5-2I Fig. 3.5-2M Fig. 3.5-2M Fig. 3.5-2N The changed areas on the revised pages are shown by marginal lines.
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Fi'gure Title 3.5-2H Operational Power Icbalance Envelope Applicable to Operation from 100t 10 to 2h6110 EFPD; Cycle 3 3 5-2I Operational Power I= balance Envelope Applicable to Operation from 2461 10 EFPD to 315 EFPD; Cycle 3 l
3.5-2J LOCA Limited Maximus A11ovable Linear Heat Rate 3 5-2K APSR Position Limits for Operation from 0 to 100+ 10 EFPD; Cycle 3 3 5-2L APSR Position Limits for Operation fres 100+ 10 to 2461 10 EFPD; Cycle 3 3 5-2M APSR Position Limits for Operation from 2h6+ 10 EFPD to 270+ 10 EFPD; l
Cycle 3 3.5-2N APSR Position Limits for Operation from 270+ 10 EFPD to 315 EFFD; Cycle 3 l 3 5-3 Incore Insti-u=entation Specification b.2-1 Souip=ent and Piping Requiring Inservice Inspection in Accordance with Section XI of the ASME Code 4.4-1 Ring Girder Surveillance k.h-2 Ring Girder Surveillance Crack Pattern Chart k.4-3 Ring Girder Surveillance Crack Pattern Chart 4.4-4 Ring Oirder Surveillance Crack Pattern Chart k.k-5 Ring Girder Surveillance Crack Pattern Chart 6-1 Organization Chart
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- I 15,0 152 Amendment No. }<,,W, jf, 38 vii
2.
The control rod group withdrawal limits (Figures 3.5-2A, 3 5-23, 3.5-2C, 3.5-23, 3.5-2E, 3.5-2F, 3.5-2K, 3.5-2L, 3 5-2M, and 3.5-2ir) shall be reduced 2 percent in power for l
each 1 percent tilt in excess of the tilt li=it.
3 The operational imbalance li=its (Figure 3 5-2G, 3.5-2H end 3 5-2I) shall be reduced 2 percent in power for each 1 percent tilt in excess of the tilt limit.
f.
Except for physics or diagnostic testing, if quadrant tilt is in excess of +25.285 deter =ined using the full incere detector systes (FIT), or +2h.095 deter =ined using the mini =us incere detector systes (MIT) if the FIT is not available, or +21.39%
deter =ined using the out of core detector system (OCT) when neither the FIT nor MIT are available, the reactor vill be Placed in the het shutdown condition. Diagnostic testing during power operation with a quadrant tilt is per=itted provided that the thernal power allevable is restricted as stated in 3 5 2.h.d above.
Quadrant tilt shall be monitored on a minicu= frequency of once 6
every tvo hours during power operation above 15 percent of rated pover.
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,b,U IJ) l AmendmentNo.g.38
control d
sitions:
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- 3.5.2.5
! 5 Operating rod group overlap shall not exceed 25 percent a.
percent, between two sequential groups except for physics tests.
Position li=its are specified for regulating and axial power b.
I shaping control reds. Except for physics tests or exercising control rods, the regulating control rod insertion /vithdrawal limits are l
specified on Figures 3.5-2A, 3.5-23, and 3.5-2c for four pu=p oper-ation and Figures 3 5-2D, 3.5-25, and 3.5-2F for three or two pu=p Also excepting physics tests or exercising centrol reds, operation.
the axial power shaping control rod insertien/vithdraval 1; sits are l
If any or specified on Figures 3.5-2K, 3 5-2L, 3.5-2M and 3 5-2:!.
these control red position limits are exceeded, corrective measures shall be taken i==ediately to achieve an acceptable centrol red position. Acceptable control red positions shall be attained within i
four hours.
Except for physics tests, power shall not be increased above the
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power level cutoff (See Figures 3 5-2A, 3 5-25 and 3.5-2c) c.
unless the xenen reactivity is within 10 percent of the equilibriu=
value for operation at rated power and asy=ptoti: ally approaching stability.
Core i= balance shall be =enitered on a =inimus frequency of once d.
every two hours during power operation above ho percent of rated Except for physics tests, corrective =casures (reduction pover.
of i= balance by APSR =cve=ents and/or reduction in reactor pover) shall be taken to =aintain operation vithin the envelope If the i= balance defined by Figures 3.5-2G, 3 5-2H and 3 5-2I.
is not vithin the envelope defined by Figres 3 5-2G, 3.5-2H a=d 3.5-2I corrective =easures shall be teken to achieve an accepta' ole If an acceptable i= baler.ce is not achieved within imbalance.
four hours, reactor power shall be reduced until i= balance limits are =et.
Safety rod limits are given in 3 1.3.5 e.
The centrol rod drive patch panels shall be locked at all ti=es vith 3.5.2.6 li=ited access to be authorized by the superintendent.
to exceed 30 effective A power =ap shall be taken at intervals not 3527 full power days using the incore instru=entation detection syste=
to verify the power distribution is within the li=its shown in Figure 3.5-2J.
Bases _
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The power-i= balance envelope defined in Ficres 3 5-2G, 3 5-2H, "nd 3 5-2! is based on LCOA analyses which have defined the =axi=u= linear hect ate (see exceed the Final Figure 3.5-2.7) such that the =sxi=u= elad te=perature vill notOperation Acceptance Criteria (2200F).
alone does not constitute a situation thet vould cau:e the Final Acceptance The power i= balance envelope Criteria to be exceeded should a LOCA c cur.
represents the toun?ary of operatica li=ited by the Final Acceptance Criteria only if the control rods are at the withdraval/ insertion li=its as derined by o
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)54 Amendment No. J(f, J(, yI, 38 h**
3-35 g
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Figures 3 5-2A, 3.5-23, 3 5-20, 3.5-2D, 3 5-2E, 3.5-2F, 3.5-2K, 2 5-2L, 3.5-2M and 3.5-2N and if quadrant tilt is at the limit. Additional conservatisn is l
introducted by application of:
i s.
Nuclear uncertainty factors b.
Ther=al calibration uncertainty c.
Fuel densification effects d.
Hot rod manufacturing tolerance factors.
e.
Postulated fuel rod bov effects The Rod Index versus A11ovable Power curves of Figures 3.5-2A, 3 5-2B, 3.5-20, 35-2D,3.5-2E,35-2F,3.5-2K,3.5-2L,3.5-2 Mand 35-2Ndescribethreeregions.l These three regions are:
1.
Per=1ssible operating Region 2.
Restricted Regions 3.
Prohibited Region (Operation in this region is not allowed)
NOTE:
Inadvertent operation within the Restricted Region for a period of four hours is not censidered a violation of a limiting condition for operation.
The limiting criteria vithin the Restricted Region are potential ejected red vorth and ICCS power peaking and since the probability of these accidents is very lov especially in a h hour time frane, inadvertant operation within the Restricted Region for a period of h hours is allowed.
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3-35a Amendment No. %% 38
Power. 5 of 2535 MWt I
RESTRICTED REGION
-31.21.102 13.7.102
-- 100 l
-28.s.90 90 80 PERMISSIBLE OPERATING 70 REGION 60 50 40 30 20 10 I
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-50
-40
-30
-20
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10 20 30 40 50 Axial Power Imaalance. 5 OPERATIONAL POWER. IMBALANCE ENVELOPE FOR OPERATION FROM 246 i 10 EFP0 TO 315 EFPD TNI-l CYCLE 3 Figure 3.5 2I 15.0 136 Amendment No.
38
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a 6.5.102 49.0.102 100 90 2.5.90 RESTRICTE0 REGION 80 2.5.80 0.80 70 60 2
49.0.60 100,60 N0 50
'a 40 PERMISSIBLE y
OPERATING E
30 REGION 20 10 I
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0 10 20 30 40 50 60 70 80 90 100 APSR t Withdrawn I
4 APSR POSITION LIMITS FOR OPERATION FROM 2461 10 EFPD TO 27 01 10 EFPD TMI-l CYCLE 3 Figure 3.5-2M j
l ;i Ainendment No.M 38
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~12.4.102 42.5.102 100 RESTRICTED NOIU 90 12.4.90 42.5.90 80 85.70 10 0 70
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N 60 N
PERMISSIBLE 50 OPERATING 100.50 REGION m
E 40 n.
30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 APSR 5 Withdrawn APSR POSITION LIMITS FOR OPERATION FROM 270 1 10 EFPD TO 315 EFP0 TMl-1 CYCLE 3 Figu r e 3.5 -2N j
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