ML20027E210
| ML20027E210 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/01/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027E211 | List: |
| References | |
| NUDOCS 8211120261 | |
| Download: ML20027E210 (8) | |
Text
o UNITED STATES "g
[ V.,,, '
p, NUCLEAR REGULATORY COMMISSION g
,j WASHINGTON, D. C. 20555 s.,...../
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-56 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated February 23, 1982, supplemented by letter dated August 3, 1982, 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.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8211120261 82110'1
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l' PDR ADOCK 05000334 P
. 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-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, 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.
F0 THE NUC, EAR REGULATORY COMMISSION t
kh a' e
Operating Reactor tranch 51 Division of Licen i
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 1, 1982 e
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ATTACHMENT TO LICEN3E AMENDMENT AMENDMENT NO. 58 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
{
Remove Pages Insert Pages 2-9 2-9 B 2-2 B 2-2 3/4 2-7 3/4 2-7 3/4 2-8 3/4 2-8 Revise Appendix B as follows*:
Remove Page Insert Page 2-2 2-2
- Due to an administrative error, this page change was not included in Amendment #55.
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TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS N
i NOTATION (Continued)
$p Operation with 3 Loops Operation with 2 Loops Operation with 2 Loops Q
(no loops isolated)
(1 loop isolated)
K
= 1.18 K
= 0.99 K
= 1.1 c-j j
j
]
K
= 0.01655 K
= 0.01655 K
= 0.01655 2
2 2
K
= 0.000801 K
= 0.000801 K
= 0.000801 3
3 3
and f (AI) is a function of the indicated difference between top and bottom detectors m
of the power-range nuclear ion chambers; with gains to be selected based on measured l
instrument response during plant startup tests such that:
(i) for q, - qh between -23 percent and + 11. percent, f ( AI) = 0 (whereq and q are percent RATED THERMAL POWER in the top and bottom halvesofthechrerespectively,andqt+9 is total THERMAL POWER in b
percent of RATED THERMAL POWER).
for each perce'nt that the magnitude of (q
-q exceeds -23 percent, (ii) the AT trip setpoint shall be automaticalfy rebu)ced by 1.54 percent of
,g its value at RATED THERMAL POWER.
Eg (iii) the AT trip setpoint shall be automaticalfy rebu)ced by 1.91 percent of for each percent that the magnitude of (q
-q exceeds + 11 percent, y
its value at RATED THERMAL POWER.
=
P EE I
SAFETY LIMITS BASES The curves are based on an enthalpy hot channel factor, dg, of 1.55 An and a reference cosine with a peak of 1.55 for axial power shape.
3 allowance is included for an increase in FaH at reduced power based on the expression:
l F'AH = 1.55 [1 + 0.3 (1-P)]
where P is the fraction of RATED THERMAL POWER These limiting heat flux conditions are higher than those calculated for the range of all control rods fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the When the limits of the f(AI) function of the Overtemperature trip.
axial power imbalance is not within the tolerance, the axial power imbalance effect on the Overtemperature AT trip will reduce the setpoint to provide protection consistent with core safety limits.
2.1. 2 REACTOR COOLANT SYSTEM PRESSURE _
The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressuri:ation and thereby prevents the release of radionucildes contained in the reactor coolant from reaching the containment atmosphere.
The reactor pressure vessel and pressurizer are designed to Section III of the ASME Code for Nuclear Power Plant which permits a 110% (2735 psig) of design pressure. The maximum transient pressure of Reactor Coolant System piping and fittings are designed to ANSI B 31.1 and the valves are designed to ASA 16.5 which permit a maximum transient pressure of 120% (2985') psig of component design pressure. The Safety Limit of 2735 psig is therefore consistent with the design criteria and associated code requirements.
The entire Reactor Coolant System is hydrotested at 3107 psig to demonstrate integrity prior to initial operation.
SEAVER VALLEY - UNIT 1 B 2-2 AMENDMENT NO. 58 i
K(Z) - MORMALIZED FQ(2)
AS A FUNCTION OF CORE HEIGHT N-LOOP BEAVER YALLEY - UNIT 1 (G.0. T.0) 3,a
_(10.8, 0. 94) 0.8 2
Yr 6
S 30.6 s
5
=:
(12, 0 431)E
~
Gy 0.,,
0.2 0
2 4
6 s
10 12 14 CORE HEIGHT (FT)
Figure 3.2-2 AMENDMENT NO. 58 BEAVER VALLEY - UNIT 1 3/4 2-7
POWER DISTRIBUTION LIMITS N
NUCLEAR INTE/LPY EOT CHANNIL FACTOR - FaH LIMIT!"G CONDITION FOR OPERATION N
3.2.3 F shall be li=ited by the following relationship:
aE N
I
- a B 5 1.55 (1 + 0.3 (1-P)]
(1-P3P(3U)]
l vhere P = TEIRVAL POLE RATED THIRMAL POWER R3P (3U) = Rod Sov Penalty as a function of region average burnup as shown in Figure 3.2-4, where a region is defined as those asse=blies with the same loading date (reloads) or enrichnent (first cores).
APPLICA3ILITY:
MODI 1 AC"' ION :
With T'I'.
exceeding its li=it:
g
- a. Reduce TdIR.dX PCb3 to less than 50% of RATID ~EIPEX POWER vithin 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-Eigh Trip Se: points to 5 55% of RATED TEIRMAL POWFR within the nex: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, N
- b. De=enstrate thru in-core =apping that F is within its li=it within AE 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the li=it er reduce *EIRMAL P0kB to less than 5% of RATID TEIP3X POWER vithin the nex: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and
- c. Identify and correct the cause of the out of 11:1: cendition prior to increasing TEILVA POWIR; subsequent POWIR OPERATION =ay proceed N
provided that F is de=onstrated :hrough in-core =apping to be with-E in its 11=1: at a no=inal 50% of RATED TEIPEX POWER prior to exceeding this TdIPEE P0k3, at a no=inal 75% of RATID EEP3.AL POWER prior to exceeding this TEIRMAL power and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95:.o'r giea:er RATIO TEIRMAI. PCLE.
l BEAVER V ALLEY-U NIT 1 3/4 2-8 AMENDMENT N0. 58 1
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i 2.3.2 Corrosion Inhibitors - (Hexavalent Chromium)'
Objective To 1Lmit the maximum concentration of hexavalent chromium at the dis-charge structure to an incremental value of 0.05 mg/1.
Specification The concentration of hexavalent chromium shall be limited to a maximum of 15 mg/l as released from the low level waste drain tanks to the cooling tower blowdown discharge as determined by analyses specified below.
Monitoring Requirement Prior to discharge, the hexavalent chromium concentration in a low level waste drain tank shall be determined by the colormetric method described on page 429 of Standard Methods for the Examination of Water and Waste Water, 13th ed, American Public Health Association. A record shall be maintained of tank concentrations of hexavalent chromium, tank discharge rates and blowdown discharge rates at times of release. An alternative equivalent method for determining the hexavalent chromium concentration may be used with the staff's approval.
Bases l
The Ohio River Valley Water Sanitation Commission recommends that the concentration of hexavalent chromium in a discharge shall not exceed 0.05 mg/1. The specified 15 mg/l release concentration with the min-f imum dilution factor of 300 assures that the concentration of the discharge to the Ohio River does not increase the concentration by more
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than 0.05 mg/1. Discharge from the low level waste drain tanks is diluted by other plant discharges so that concentration in the tanks will be decreased by a factor of 300.
2-2 AMENDMENT NO. 55
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