ML19318A800
| ML19318A800 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/06/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19318A797 | List: |
| References | |
| NUDOCS 8006240175 | |
| Download: ML19318A800 (10) | |
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UNITED STATES y ); c.
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NUCLEAR REGULATORY COMMISSION 5
E WASHINGTON, D. C. 20555
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMEf;DMEf;T TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-1 1.
The i;uclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensees) dated December 24, 1979, as supplemented March 4 and 17, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1980, complies with the standards and re 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 pro-visions of the Act, and the rules and reguistions of the Commission; C.
There '
reasonable assurance (i) that the activities authorized by this anendment 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 Cor:raission's regulations and all applicable requirements have been satis-fied.
2.
A:cordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) cf Facility Operating License No. NPF-1 is hereby amended to read as follows:
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TrojanHudlear' Plant (2) -Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license.. The licensee shall operate the facility in
'accordance with the Technical Specifications, except as noted in paragraph 2.C.(10) below, 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REPJLATORY COMMISSION Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 6, 1980 e
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 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-4 corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 1-24 3/4 2-6a 3/4 2-8 8 3/4 2-5' A 44W M.
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r REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.5 The control banks shall be limited in physical insertion as shown_in Figures 3.1-1 and 3.1-2.
APPLICABILITY: MODES 1* and 2*!.
ACTION:
With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:
a.
Restore the control banks to within t.he limits within two hours, or
.b.
Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or c.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.5 The position of each control bank shall be determined to be within the insertion limits at.least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- See Special Test Exceptions 3.10.2 and 3.10.4.
- With K,ff 2.1.0.
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FRACTION OF RATED THERMAL POWER 1
Figure 3.1-1 l
l Rod Bank Insertion Limits Versus Thermal Power Four Loop Operation i
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i TROJAN-tJNIT 1 3/4 1-24 Amendment No. 44
POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued)
'b)
At least once per 31 EFPD, whichever occurs first.
RTP 2.
When the F is less than or equal to the F limit fe x
the appropriate measured core plane, additional power distribution maps shall be takon and F compared to R
F,TP and F at least once per 31 EFPD x
1 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 either bank x"0" control rods or any part length rod.
RTP 2.
F 1 1.65 for unrodded core planes.
x f.
The F,y limits of e, above, are not applicable in the fol-lowing core plane regions as measured in percent of core 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 1 2%, 32.1 1 2%, 47.4 1 2%,
60.6 + 2% and 74.9 + 2%, inclusive.
4.
Core plane regions within + 2% of core height (+ 2.88 inches) about the bank demand position of the bank "D" or part length control rods.
g.
Evaluating the effects of F on F (Z) to deterr ine if F (Z) xy 9
9 is within its limit whenever F exceeds F xy xy*
4.2.2.3 F (Z) shall be measured at least once per 31 EFPD.
When F (Z) is q
9 measured, an overall measured value shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
TROJAN-UNIT 1 3/4 2-6a Amendment No. 6, 3D,44
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TROJAN-UNIT 1 3/4'2-7 1
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o POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F AH LIMITING CONDITION FOR OPERATION 3.2.3 F shall be limited by the following relationship:
AH N
3H 1 1.55 [1.0 + 0.2 (1-P)]
F where P = THERMAL POWER RATED THERMAL POWER APPLICABILITY: MODE 1 ACTION:
With F exceeding its limit:
H a.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 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-High Trip Setpoints to 1 55% of RATED THERMAL POWER within the next 4
- hours, N
b.
Demonstrate thru in-core mapping that F 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 limTU 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 />, and c.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION N
may proceed provided that F is demonstrated through in-core mapping to be within its likt at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL 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% or greater RATED THERMAL POWER.
TROJAN-UNIT 1 3/4 2-8 Amendment No. 30, 44
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POWERDISTRIBUTiONLIMITS BASES a.
abnormal perturbations in the radial power shape, such as from more directly than F,
rod misalighment, effect F H g
b.
although rod movement has a direct influence upon limiting Fq to within its limit, such control is not readily available to limit N
F3H, and c.
errors in prediction for control power shape detected during startup physics tests can be compensated for in Fq by restri-ting axial flux distributions. This compensation for F is H
less readily available.
The radial peaking factor, Fxy(Z), is measured periodically to provide additional assurance that the heat flux hot channel factor, q
xy(Z) limits were detennined from F (Z), remains within its limit. The F expected power control maneuvers over the full range of burnup conditions in the core.
Fuel rod bowing reduces the value of the DNB ratio and F Sufficient H.
credit.is available tr 7ffset this reduction.
This credit comes from generic design margins totaling 9.1%, 2% increased flow over the flow assumed in the safety analyses (as listed in Table 3.2-1) and 3% margin in the difference between the 1.3 DNBR safety limit and the minimum DNBR calculated for the Complete Loss of Flow event.
TROJAN-UNIT 1 B 3/4 2-5 Amendment No. 30,44
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POWER DISTRIBUTION LIMITS BASES 3/4.2.4 QUADRANT POWER TILT RATIO 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 measurenents are made during startup testing and periodically during power operation.
-The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting 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 n
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 reducing the power by 3 percent for each percent Of tilt in excess of 1.0.
3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed.in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.
In Table 3.2-1, for 4 loop operation, credit is being taken for the actual reactor coolant flow rate being 102 percent of the design value.
From Trojan tests, a primary system flow calorimetric calculation indicated a flow rate of 7 percent in excess of design.
Similarly, the pump-power relationship demonstrated that the reactor coolant flow rate was 3.5 percent in excess of design. The large margin between these excess flow indications ~ and the 102 percent of desi n flow specified in Table 3.2-1 assures that the uncertainties in the cal-culation of the actual reactor coolant flow rate are accounted for.
l The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters thru instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.
The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.
TROJAN-UNIT 1
.B 3/4 2-6 Anendment No.30 1
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