ML17053A989
| ML17053A989 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  (DPR-63-A-034, DPR-63-A-34) |
| Issue date: | 08/10/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17053A990 | List: |
| References | |
| NUDOCS 7909110106 | |
| Download: ML17053A989 (10) | |
Text
o~ "~GIIC
+
0 gy
'L p Q kg~*+
UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
34 License Ho.
DPR-63 1.
The A.
Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated July 19,
- 1979, 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.
C.
r
~
~
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicaole requiremen:s 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 Ho.
DPR-63 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 34, are hereby incorporated in the license.
The licensee shall operaTe the facility in accordance wi th the Technical. Specifications.
v909~lo 1 O~
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August lO, lg7g Operating Reactors Branch 83 Division of Operating Reactors
ATTACHMENT TO LICENSE AMENDMENT NO.
34 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220
~
~
Revise Appendix A by removing pages 64a and 70a and replacing with revised pages 64a and 70a.
Marginal lines indicate area of change.
LIHITItlG COtlOITIOtl FOR OPFRATIOlf SURVEILI.Al)CE REqUIREHEHT Hfrrfmrr>>r Critical Power Ratio HCPR Drrrfng power operation tlCPR slral1 be
> 1.40 for GxG fuel and
> 1.37 for GxGR fuel at rated power and flow. If at any tir>>e during power operation it is det,ermined by norr>>al surveillance Llrat Llrese ll>>rits are no longer met, action slrall be initiated within 15 mirrrrLes Lo restore'peration to wiLlrin Lire prescribed 1 ir>>l ts.
I f al I tire opera t ing llCl'Rs are not returned to wftlrfn Lire prescribed Iir>>its wiLhin Lwo (2) lrours, reacLor power reductions slrall be initiated aL a raLe not less than IOX per lrour until tlCI'R is within Lhe prescribed limits.
c.
Hfnfmum Critical Power Ratio llCPR HCPR sha11 be determined daily during reactor Power operation at >25% rated tlrermal power.
d.
Power Flow Relatfonshf Co>>rplfance with the power flow relationship in Section 3.1.7.d slrall be determined daily during reactor operation.
lor core flows oLher than rated Lire llCPR li>>rits slrall be Lhe limits identified above times Kf <<lrere Kf fs as shown fn Figrrre 3.1.7-1.
Power Flow Rela L I onslr f Orrrin Power 0 era tion llr>> power/flow re1atfonshfp slrall not exceed Lhe lirrritirrg values slrown in Ffgrrre 3.1.7.aa.
When operating with one recirculation loop
- isolated, the reactor may operate at 100 percent of full licensed power level provided the following conditions are met; l.
Suction valve, discharge valve and discharge bypass valve in the isolated loop shall be in the closed position and the associated motor breakers shall be locked and tagged in the open position.
2.
Associated pump motor circuit breaker shall be
- open, tagged, and the breaker removed.
If these conditions are not met, core power shall be restricted to 90.5 percent of full licensed power.
64a
OASES FOR 3.1.?
NID 4.l. / FUEL RODS of the plant, a
HCPR evaTuatfor) wflf be made at the 251 tf)ermaf power level with minimum recirculation pump speed.
The IICPA o)argin will tl)us bc dco)onstrated sucl) tl))t futuro llCPA evaluations below this power level will be shown to be unnecessary.
The daily rcqutrement f<)r calculating tlCPA ahoye 251 rated tl)crmal power is sufficient since po)rer distribut.ion shifts are very slo)<r when there have not been significant power or conLrol rod ch)))yes.
The requirement for calculating HCP!t )rl)en a limiting control rod pat'tern is approached ensures that IICI'A wi'll be known following a char)gc in power or power shape (regardless of magnitude) that coul>re 3.1.7-1 is used for calculaLing llCPA during operation at other than rate>g at Lhe no)olna1 rerlui) cd IICPA at 1001 power.
For <<)anual flow co))L) r)l, lhe Kf is dl ter<<)ine)I sucl) that an inarlvertcnt increase. in core flow (i.e., operator error or rcci)'culutlon p>><op speed controller failure) would result in arriving at Lhc 99.95 liroit IICI'A when core flow reaches thc roaxi<<o<<o possible core flo)r corrcsponrlln<j to a part.icular setLing of the recirculation pu)op IIG set:cool)
L>>hc <<)aximu<o speed control lio)iting seL screws.
These screws are to bc calibrated and set Lo a pa) Licular value and whenever Lhe plant is operating in n)anual flo)r control the Kf defined by that. setting of the screws is Lo be used in Lhe {lctcr)oi))ation of required I1CPA.
This will assure that Lhe reduction in IICPA aSSnCiaLCd With an inadVCrtent flOW inCreaSe alWayS SatiSfiCS Lhe 99.9X rertuirCO)ent.
irreSpeCtiVe Of I,hc scoop t>>bc s e ttinq, the rcqui rcd IICPA i s never a 1 1 o)'rcd Lo be less than Lhc r)oo)i na 1 lICPA (i.e., Kf is
>>ever less t.han unltyJ.
.P ~FI<<B 1
1
~Ll The po)rc)'/flo)r ci))'vc is the locus of critical po)rer as a function of flow from which the occurrence of abnor<<)al operating transients will yield results within defi))ed plant safety limits.
Each transient and posL>>late>stifles the operating envelope bounded by the power/floe curve as long as other operating limiLs a).c satisfied, Operation under the power(Flow 1$ >>e is designed to enable thc direct ascension to full po)'lcr )rit.hin the design basis for tl)e plant.
L The requirco<cnts of Specification 3.1.7d for isolated loop operation precludes the inadvertent start-up of a recirculation pump with a cold leg.
Ilowever, if these conditions cannot be met, power level is restricted to 90.5 percent power based on current transient analysis.
70a
I