ML20245C313
| ML20245C313 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/12/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245C312 | List: |
| References | |
| TAC-6811, NUDOCS 8710260058 | |
| Download: ML20245C313 (13) | |
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UNITED STATES l
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NUCLEAR REGULATORY CCMMISSION
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1? h W ASHINGTON, 0. c. 20565 i
I DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY i
PENNSYLVANIA POWER COMPANY 00CKET NO. 50-33' l
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BEAVER VALLEY POWER STATION UNIT NO. 1-l AMENOMENT TO FACILITY OPERATING LICENSE
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Arrendment No. 9 License No. DPR-66
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The Nuclear Regulatory Comission-(the Comission) has found that:
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- A. The application for amendment by Ducuesne Light Company, filed on behalf of itself, Ohio Edison Company, and Pennsylvania l
Power Company (the licensees) dated February 11, 1977, 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 Ccmnission; 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 actfvities will be conducted in compliance with the Comission's regulations; 0.
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 Par.
j 51 of the Comission's regulations and all applicable requirements have been satisfied.
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i 8710260058 770712 ADOCK 05000344 PDR PDR i
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachtnent to this license arnendment, and paragraoh 2.C.(2) of Facility Operating License
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1 No. DPR-66 is hereby arnended to read as followsi
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r (2) Technical Specifications The Technical Specifications contained in-Appendices A and. B, as revised through Amendment No.
9, are hereby incorporated in the license. The licensee I
I shall operate the f acility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its l
issuance.
i FOR THE @ CLEAR REGULATORY COMMISSI0ft I
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4 Robert >'. Reid, Chief Operating Reactors Branch !?
Division of Operating Reactors Attachtnent:
Changes to the Technical Specifications Date of Issuance:
July 12,1977 e
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 9 FACILITYOPERkTINGLICENSENO.OPR-66 DOCKET N0'. 50-334 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided-to maintain document completeness.
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X l-3/4 2-1 A (deleted) l 3/4 2-2A (deleted) l 3/4 2-3A (deleted) 3/4 2-4A (deleted) l 3/4 2-1B 3/4 2-2B 3/4 2-38 d
3/4 2 dB 3/4 2-5 3/4 2-6a i
3/4 2-14 (deleted) i 3/4 2-15 (deleted) 3/4 2-16 (deleted) 3/4 3-47 (deleted) 3/4 3-48 (celeted)
B 3/4 2-1 B 3/4 2-2 8 3/4 2-6 8 3/4 3-3 l
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Pace 3/4.0 APPLICABILITY.............................................
3/40-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL
> 200*F..........................
3/4 1-1 Shutdown Margin - Tavg avg 200*F..........................
3/4 1-3 Shutdown Margin - T Boron Dilutio1.........................................
3/4 1-4 Moderator temperature Coefficient.......................
3/4.1-5 Mi nimum Tempe'rature for :C~ri tical ity....................
3/4 1-6 3/4.1.2 B0 RATION SYSTEMS l
t Flow Paths - Shutdown..................................
3/4 1-7 l
1 Fl ow P a th s - O p e ra t i n g.................................
3/4 1-9 Charging Pump -
Shutdown...............................
3/4 1-11 f
Cha rgi ng Pumps - Opera ti ng.............................
3/4 1-12 Boric Acid Transfer Pumps - Shutdowri...................
3/4 1 13 q
Bo ri c Aci d Transfer Pumps - Opera ti ng..................
3/4 1-14 Bora ted Wate r Sources - Shutdown.......................
3/4 1-15 l
Borated Water Sources - Operating......................
3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES l
Group Height...........................................
3/4 1-18 l
Posi tion Indi cator Channel s............................
3/4 1-20 l
l Rod Orop Time..........................................
3/4 1-21 Shutdown Rod Insertion Limit...........................
3/4 1-22 Co ntrol Rod In se rti on L imi ts...........................
3/.4 1-23 i
Part Length Red Insertion Limits.......................
3/4 1-26 l
BEAVER VALLEY - UNIT 1 III h_______
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE 3/4.9.10 WATER LEVEL-REACTOR VESSEL.............................
3/4 9-10 7
l 3/4.9.11 STORAGE POOL WATER LEVEL...............................
3/4 9-11 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM - FUEL M0VEMENT.............................................
3/4 9-12 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM - FUEL ST0 RAGE..............................................
3/4 9-13
?,/ 4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN........................................
3/4 10-1 3/4.10.2 GROUP HEIGHT AND INSERTION LIMITS......................
3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY...
3/4 10-4
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3/4.10.4 PHYSICS TEST...........................................
3/4 10-6 1
3/4.10.5 NO FLOW TESTS.........................................
3/4 10-7 1
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l BEAVER VALLEY - UNIT 1 IX Amendment No. 2
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1 3/4.2 POWER DISTRIBUTION LIMITS
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AXIAL FLUX DIFFERENCE (AFD)
LIMITING CONDITION FOR OPERATION I
3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained I
i within a i 7% target band (flux difference units) about the target flux difference.
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i APPLICABILITY: MODE 1 ABOVE 50% RATED THERMAL POWER
- ACTION:
a.
With the indicated AXIAL FLUX DIFFERENCE outside of the + 7%
target band about the target flux difference and with THERMAL POWER:
1.
Above 90% of RATED THERMAL POWER, within 15 minutes:
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a)
Either restore the indicated AFD to within the target i
band.11mits, or b)
Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.
2.
Between 50% and 90% of RATED THERMAL POWER:
a)
POWER OPERATION may continue provided:
1)
The indicated AFD has not been outside of the 17% target band for more than 1# hour penalty deviation cumulative during the previous 24 i
i hours, and 2)
The indicated AFD is within the limits shown on Figure 3.2-1.
Otherwise, reduce TBERMAL POWER to l
1ess than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range. Neutron Flux-High Trip Setpoints to < 55% of RATED THERMAL POWER within the next 4'nours.
bl Surveillance testing of tbe Power Range Neutren Flux Channels may be perforr,ed pursuant to Specification 4.3.1.1.1 provided the indicated AFD is maintained within the limits of Figure 3.2-1.
A total of 16 I
hours operation may be accumulated with the AFD outside of the target band during this testing without penalty deviation.
- See Special Test Exception 3.10.2
- A 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> penalty deviation is permissible during tests performed as part of the Augmented Startup Test Program.
BEAVER VALLEY - UNIT 1 3/4 2-1 Amendment No. 9 l
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.3 The target flux difference of each OPERABLE excore channel l
shall be. determined by measurement.at least once per 92 Effective Full Power Days with all part length control rods fully withdrawn. The pro-
' lit visions of Specification 4.0.4 are not applicable.;
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4.2.1.4 The target flux difference shall be updated at least once per l
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31 Effective Full Power Days by either determining the target flux
. s difference pursuant to 4.2.1.3 above or by linear interpolation between l
the most recently measured value and 0 percent at the end of the cycle 7
life.
The provisions of Specification 4.0.4 are not applicable.
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1 SEAVER VALLEY - UNIT 1 3/4 2-3 AmendmentNo.[,9 l
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POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F (Z) n LIMITING CONDITION FOR OPERATION 3
3.2.2 F (Z) shall be limited by the following relationships:
g F (Z) 1[2.32] [K(Z)] for P > 0.5 g
F F (Z) 1 [(4.54)- [K(I)] for P 1 0.5 g
THERMAL POWER where P =
RATED THERMAL POWER and K(Z) is the function obtained fror Figure 3.2-2 fnc a given core height location.
APPLICABILITY: MODE 1 ACTION:
With F (Z) exceeding itis limit:
q Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the a.
4imitwithin15minutesandsimiliarlyreducekhePowerRange Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower aT Trip Setpoints have bee'n reduced at least 1% for each 1%
F (Z) exceeds the limit.
The Overpower ai Trip Setpoint i
oreduction shall be perfomed with the reactor suberitcal.
b.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; THERMAL POWER may then be increased provided F (Z) is demonstrated through fncore 9
mapping to be within its limit.
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SEAVER VALLEY - UNIT 1 3/4 2-5 Amendment No. 9
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j POWER DISTRIBUTION LIMITS _
j SURVEILLANCE REQUIREMENTS (Continued) b)
At least once per,31 EFPD, whichever occurs first.
f is less than or equal to the Ffy C
limit for-2.
When the Fxy the appropriate measured core plane', additional power distribution maps shall be taken and F compared to i
P F
and F at least once per 31 EFPD x
x e.
The F limits for RATED THERMAL POWER within specific core xy planes shall be:
RTP 1.
F 1 1.71 for all core planes containing bank "D" x
control rods arid /or any part length rods, and RT F[1 1.55 for all unrodded core planes.
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The F limits of e, above, are not appl.icable in the fol-
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xy lowing core plane regions as measured in percent of. core
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height from the bottom of the ' fuel:
1.
Lower core region from 0 to 15%, inclusive.
2.
Upper core region from 85 to 100% inclusive.
3.
Grid plane regions at 17.8 + 2%, 32.1 + 2%,
46.3 + 2%, 60.6 + 2% and 74 9 + 2%, in 1usive.
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Core plane regioiis within + 2% of core height (+ 2.88 inches) about the bank demand position of the bank "D" or part length control rods.
WithFfexceedingFf g.
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The F (Z) limit shall be reduced at least 1% for each g
l% F exceeds Fx, and i
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The effects of F on F (2) shall be evaluated to determine xy 9
ifF(Z)iswithinitslimit.
g 4.2.2.3 When F (Z) is measured pursuant to Specification 4.10.2.2, an g
overall measured F (Z) shall be obtained from a power distribution map g
and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
BEAVER VALLEY - UNIT 1 3/4 2-6a AmendmentNo.[,9 O
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3/4.2 POWER DISTRIBUTION LIMITS t
o BASES L
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I The specifications of-this section provide assurance of fuel integ-rity during Condition I (Normal Operation) and. II (Incidents of Moderate i
Frequency) events by:
(a) maintaining. the minimum. DNBR in the core >
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1.30 during normal operation and in~short term transients, and (b)
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limiting the fission gas release, fuel pellet temperature & cladding.
mechanical properties to.within assumed' design' criteria.:, In' addition, b'
limiting the peak' linear power density during Conditions I. events pro-vides assurance that the initial conditions assumed for the LOCA analyses l
are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.
The definitions of hot channel factors as used in these specifi-cations are as follows:
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F (Z)
Heat Flux Hot Channel Factor, is defined as the maximum local Q
heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for man-ufacturing tolerances en fuel pellets and rods.
F)H Nucidar Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.
i 3/4.2.1 AXIAL FLUX DIFFERENCE (AFO)
The limits on AXIAL FLUX OIFFERENCE assure that the Fn(Z) upper bound envelope of 2.32 times the normalized axial peaking Yactor is not t
I exceeded during either normal operation or in the event of xenon re-distribution following power changes.
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Target flux difference is determined at equilibrium xenon condi-tions with the part length control rods withdrawn frem the core.
The full length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL pCWER for the associated core burnup condi-tions. Target flux differences for other THERMAL POWER levels are BEAVER VALLEY - UNIT 1 B 3/4 2-1 Amendment No. 9 i
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POWER DISTRIBUTION LIMITS BASES i
abnornal perturbations in ghe radial power shape, such as from l
a.
rod misalignment, effect F more directly than F,
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although rod movement' has a direct influence upon limiting F to b.
wjthin its limit, such control is not readily available to 19mit F3g, and c.
errors in prediction for control power shape detected during startup physics tests can be compensated for in Fg byrgstri-ting axial flux distributions. This compensation for F is y
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i less readily available.
1 3/4.2.4 QUADRANT POWER TILT RATIO j
LL-The quadrant power-tilt ratio limit assures that the radial power..
-distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup i
testing and periodically during power operation.
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The limit of 1.02 at which corrective action is required provides DNS and linear heat generation rate protection with x-y plane power tilts. A 14m'iting tilt of 1.025 can be tolerated before the margin for uncertainty in F is depleted. The limit of 1.02 was selected to provide an allowance g
I for the uncertainty associated with the indicated power tilt.
The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and cor-rection of a dropped or misaligned rod.
In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by l
l reducing the power by 3 percent for each percent 9f tilt in excess of 1.0.
SEAVER VALLEY - UNIT I B 3/4 2-5 W
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I INSTRUMENTATION BASES 1
3/4.3.3.5 REMOTE SHUT 00WN INSTRUMENTATION l
The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of I
HOT STANOBY of the facility from locations outside of the control room.
This capability is required in the event control roem habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
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SEAVER VALLEY - UNIT 1 B 3/4 3-3 Amendment No. 9
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