ML20206E048
| ML20206E048 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/07/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20206E052 | List: |
| References | |
| NPF-49-A-027 NUDOCS 8811170378 | |
| Download: ML20206E048 (9) | |
Text
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UNITED STATES g
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NUCt.FAR REGULATORY COMMISSION L
E W ASHINGTON, D. C. 20655
,o NORTHEAST NUCLEAR EN_ERGY COMPAN_Y. ET AL.*
D_0CKET NO. 50-423 MILLSTONE N_UCLEAR P0_WER STATION _,_ UNIT NO. 3 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-49 1.
The Nuclear Re'gulatory Comission (the Comission) has found that:
I A.
The application for anendment by Northeast Nuclear Energy Company, et al. (the licensee) dated September ?, 1988, 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 (i) that the activities authorized by c
this atendment can be conducted without endangering the health ard l
safety of the public, and (ii) that such activities will be conducted in compliarce with the Comission's regulations; D.
The issuance of this amendnent 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 l
l been satisfied.
i
- Northeast Nuclear Energy Company is authorized to act as agent and represent-i ative for the following Owners:
Central Maine Power Company, Central Vermont i
Public Service Corporation, Chicopee Municipal Lighting Plant, City of Burlington, Vermont, Connecticut Municipal Electric Light Conpany, Massachusetts Municipal Wholesale Electric Company Montaup Electric Company, New England Power Company, The Village of Lyndonville Electric Departrent, Western Massachusetts Electric Company, and Verront Electric Ger>eration ard Transmission Cooperative. Inc., and has exclusive responsibility and control over the physical construction, operation and paintenance of the facility.
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8911170376 G01107 PDR ADOCK 05000423 P
PDC l,
-2 2.
Accordingly, the license is arrended by changes to the Technical Specifications as indicated in the attachnient to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the i
Environtrental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be l
ieplemente'd within 3C days of issuance.
FOR THE NUCLEAR REGUI,ATORY COMPISSION PrSj'ectDirectorateI-e)
Jp F. Stolz, Director Division of Reactor Projects 1/I!
Office of Nuclear Reactor Regulation Attachtrent:
Changes to the Technical Specificatieris Cate of Issuance: November 7, 1988 Y
e
ATTACHVENT T,0,M CENSE M EADp,Epl 10,47,,
fACILT1YOPERATINGLICENSENO.NPF-49 A
DOCKET NO.,5,0,,4,23 Replace the following pages of the Append'x A Technical Specifications with the enclosed pages. The revised pages are identified by amendment nurr.ber and contain vertical lines indicating the areas of change. Any corresponding 1.
overleaf pages are provided to maintain document completeness.
Remove Insert c
3/4 2-17 3/4 2-17 3/4 2-19 3/4 2-19 B 3/4 2-6 B 3/4 2-6
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POWER DISTRIBUTION LIMITS SURVElllANCE RE0VIREMENT (Continued) 4.2.3.1.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months. Within 7 days prior to performing the precision heat balance, the instrumentation used for determination of steam pressure, feedwater pressure, feedwater temperature, and feedwater venturi JA P in tie calorimetric calculation
- shall be calibrated.
1 4.2.2.1.6 If the feedwater venturis are not inspected and 6:eaned at least once per 18 months, an additional 0.1% will be added to the total RCS flow measurement uncertainty.
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1
.I MILLSTONE UNIT 3 3/4 2 17 Ameadnent No. 27
POWER DISTRIBUTION LIMITS R05 FLOW RATE AND NUOLEAR ENTHAL?Y RISE HOT CHANNEL FACTOR THREE LOOPS OPERATINO LIMITINO CONDITION FOR OPERATION 3.2 3 2 The indleated peactor Ceolant Systes (RCS) total flow rate and FN shall be maintained as follows:
H a.
ROS total flow rate Jt 304,780 spa, and
[,1.0+0.43(1.0-P{
b.
F 1 351 bH Where:
A THERMAL POWER g) p RA ED THERMA. POWER N
- 2) F,g Measured values of F obtained by using the novatie intore detectors to obtain a power distribution sap.
Tne'seasared value of F",g should be used since Spe:1-fication 3 2 3 2b. takes into consideration a sensure.
ment uncertainty of 45 for incere measurement, and 3) 7ne measured value of ROS total flow rate shall be used since uncertainties of 2.0% for flos measurement have beer, included in Specification 3 2 3 2a.
APPLI0 ABILITY:
MOOI 1.
A:7301:
Vitn the R:S total flow rate or T,g outside the region of acceptable operation:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
- 1.
Bestore the ROS total flow rate and F t within the above limits, or 6H 2.
Reduce THERMAL POWER to less than 325 of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip setpoint to less than or equal to 375 of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
t MILLSTONE - UNIT 3 3/4 2-18 Abendment No. 12 i
I I
POWER DISTRIBUTION LIMITS L'MITING CONDITION FOR OPERATION ACTION (Continued) b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits, verifyNthrough incore flux mapping and RCS total flow rate that F and RCS total flow rate are restored to within the aboveYmits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b., above; H subsequent POWER OPERATION may proceed provided that F*H and indicated RCS total flow rate are demonstrated, through incere flux mapping and RCS total flow rate comparison, to be within the region of acceptablo operation prior to exceeding the following THERMAL POWER levels:
1.
A nominal 32% of RATED THERMAL POWER, and 2.
A nominal 50% of RATED THERMAL POWER.
SURVEILLANCE RE0VIREMENT (Continued) 4.2.3.2.1 be provisions of Specification 4.0.4 are not applicable.
N 4.2.3.2.2 Rss iotal flow rate and F shall be determined to be within the acceptable.&nge at least once peY 31 Effective Full Power Days.
4.2.3.2.3 The indicated RCS total flow rate shall be verified to be withintheacceptablerangegtleastonceper12hourswhenthemost recently obtained value of FAH, obtained per Specification 4.2.3.2.2, is assumed to exist.
4.2.3.2.4 The RCS total flow rate indicators shall be subjected to a
(
CHANNEL CAllBRATION at least once per 18 months. The measurement l
instrumentation shall be calibrated within 7 days prior to the performance of the calorimetric flow measurement.
4.2.3.2.5 The RCS total flow rate shall be deterstned by preefsion heat balance measurement at least once per 18 months. Within 7 days prior to performing the precision heat balance, the instrumentation used for determination of steam pressure, feedwater pressure, feedwater temperature, and feedwater venturt AP in tie calorimetric calculations shall be calibrated.
4.2.3.2.6 If the feedwater venturis are not inspected and cleaned at least once per 18 months, an additional 0.1% will be added to the total RCS flow measurement uncertainty.
MILLSTONE UNIT 3 3/4 2 19 A=endnent No. 27
POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not excee' 1.02.
APPLICABILITY: MODE 1, above 50% of RATED THERMAL POWER *.
ACTION:
a.
With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:
1.
Calculate the QUADR %NT POWER TILT RATIO at least once per nour until either:
a)
The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)
THERHAL F0WER is reduced to less than 50% of RATED THERHAL POWER.
2.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
I i
a)
Reduce the QUADRANT POWER TILT RATIC to within its limit, or b)
Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRAN1 POWER TILT RATIO in a
excess of 1 and similarly reduce the Power Range Neutron i
Flux-High Trip Setpoints within the aext 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Verify that the QUADRANT POWER TILT RA1IO is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERHAL POWER to less than 50% of RATED THERHAL POWER within the next i
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux Hi0h Trip Setpoints to less than or equul to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; and 4,
Identify and correct the cause of the out-of-limit condition prior to increasing THERHAL POWER; subsequent POWER OPERATION I
above 50% of RATED THERMAL POWER may proceed provided that the i
QdADRxNT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable.. 95%
or greater RATED THERHAL POWER.
l t
- $ee Special Test Exceptions Specification 3.10.2.
I MILLSTONE - UNIT 3 3/4 2-20 3
o
,O PohTF DISTFI?UTION LIMITS BASES HEAT FLUX HOT CHANNEL FA0707 AND RCS FLOW RA7E AND NUOLEAR ENTHALPY RISE HOT CHANNEL FACTOP (Continuec) c.
The control rod insertion limits of Specifications 313 5 and 3 1 3 6 are maintained; and d.
The axial power distribution, expressed in teras of AX1AL TLUX D1TTERENCE, in saintained within the limits.
F throughh.w!!!besaintainedwithinitslimitsprovidegConditionsa.
above are maintained. The relaxation of Fa y as a function of THERv.AL P0hTR illows changes in the radjel power shape for all per:issible red insertion limits.
The T1g as calculated in Specifications 3 2 3 1 and 3.2 3 2 are g
used in the varloaa accident analyse.* uhere F influences parameters 4
etner tha. 0?GF, e.g., peak clad temperature, aNd thus is the maxima:
'as neasared' value allowed.
Tr.e differer.ce betwegn the three and four-loop F,y,used in the safety i
is due to a e:re restrictive Ta for threg-loop op e ra t i er..
In fear-lo.; operatien, the allowable seasured F g calcalated ir. Specificatibn 3 2 31 at 655 Raged Thermal Power is 6 '.65.
Ir. three-loe; c;eration, however, T ! safety analyses for is restricted to a f 1.55 to be consistent with th cessared value three loc;g ;eration. At zero po'ner, both specifications allow the sa=e o
messared T3 g.
Fuel rod bowing reduces the value of DN3 ratio.
Credit is
- i available to offset this reducti-in the generie s,argin. The generic l
margint, tetaling 9.11 ON3R co:pletely offset any rod bow penalties.
Tnis cargin incluces the followins 4
a.
Design limit DN37 of 1 30 vs 1.28, b.
Oric Spacira (K i of 0.0146 vs. 0.059, c.
7neraal Diffusion Coeffielent of 0.035 vs 0.059, d.
DiGP Maltipiter of 0.66 vs. 0.86, and e.
Pitch redaction.
The applicable values of rod bow penalties are referenced it, the FSAR.
MILLSTONE - UNIT 3 8 3/4 P-$
Amendrnent No.12 l
=
j POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHI,LPY DISE HOT CHANNEL JACTOR (Continued)
When an F measurement is taken, an allowance for both experimental errorandmanu9acturingtolerancemustbemade. An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance.
The Radial Peaking Factor, F provide assurance that the Hot ChEn(Z), is measured periodically to el Factor, F (Z), remains within its g
RTP limit. The F limit for RATED THERMAL POWER (F RadialPeakinffactorLimitReportperSpecificaNon)6.9.1.6wasas provided ir. the
(
determined from expected power :ontrol manuevers over the full range of burnup conditions in the core.
I When RCS flow rate auf F are measured, no additional allowances I
N are necessary prior to compirNon with the limits of the Limiting j
Condition for Operation. Measurement errors of 1.8% for four loog flow and 2.0% for three loop flow for RCS total flow rate and 4% for F have J
been allowed for in determination of the design DNBR value.
AH i
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The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators.
Potential fouling of the feedwater venturi which might not be detected could bias the result from the i
precision heat balance in a nonconservative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi will be added if venturis are not inspected and citaned at least once per 18 months Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending various
]
plant performance parameters.
If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall oe cleaned to eliminate l
the fouling.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of indicated RCS flow is sufficient in detect only flow degradation which could lead to operation i
outside the acceptable region of operation defined in Specifications 3.2.3.1 and 3.2.3.2.
3/4.2.4 OUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power l
distribution satisfies the design values used in the power capability analysis. Padial power distribution measuremeats are made during STARTUP i
j tecting and periodically during power operation, t
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J MILLSTONE. UNIT 3 8 3/4 2 6 Amendment 30, 27 L
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