ML20235F674
| ML20235F674 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/23/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F676 | List: |
| References | |
| NUDOCS 8709290273 | |
| Download: ML20235F674 (8) | |
Text
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![p sicg('o UNITED STATES g
NUCLEAR REGULATORY COMMISSION r
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PilRLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-70 The Nuclear Regulatory Comission (the Commission or the NRC) has found 1.
that:
The application for amendment filed by the Public Service Electric &
A.
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licenseesi dated October 3, 1986, 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; The facility will operate in confonnity with the application, the B.
provisions of the Act, and the rules and regulations of the Comission; (1) that the activities authorized by There is reasonable assurance:
C.
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 Comission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the comon D.
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 E.
the Comission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifica-2.
tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
8709290273 B70923 PDR ADOCK 05000272 PDR P
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, 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 its date of issuance.
FOR THE NVCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Septenber 23, 1987 I
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. E2, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
0
. Walter.R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes tn the Technical Specifications Date of issuance: Septu6er 23,1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO.
82 1
FACILITY OPERATING LICENSE NO. DPR-70
(
DOCKET NO. 50-272 s
Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 2-7 3/4 2-7 3/4 2-7a*
3/4 2-7a*
B 3/4 2-5 8 3/4 2-5 B 3/4 2-6*
B'3/4 2-6*
I
4 POWER DISTRIBUT ION LIMITS SURVEILLANCE RE0V[REMENTS (Continued) b) At least once per 31 EFPD, whichever occurs first.
C RTP 2.
When the F xy is less than or equal to the Fxy limit for the appropriate measured core plane, additional power distribution maps C
RTP L
shall be taken and Fxy compared to Fxy and Fxy at least once per 31 EFPO.
e.
The F limit f or Rated Thermal Power (f x shall be provided f or xy all core planes containing bank "0" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.9.
limits of e, above, are not applicable in the folicwing core The Fxy f.
plane regions as measured in percent of core height from the bottom of the fuel:
1.
Lower core region f rom 0 to 15% inclusive.
2.
Upper core region from 85 to 100% inclusive.
I 3.
Grid plane regions at 17.8 + 2%, 32.1 + 2%, 46.4 + 2%,
l 60.6 + 2% and 74.9 + 2% incTusive.
+ 2.88 inches) about l
Core iilane regions within + 2% of core height (T rods.
4.
the bank demand position of the bank "U" contro l
Evaluating the ef fects of Fxy on FQ(Z) to determine if F (Z) is Q
g.
l C
L is within its limit whenever Fxy exceeds Fxy.
S A LIM - UN IT 1 3/4 2-7 Amendment No. 82
4 POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued) 4.2.2.3 When F (Z) is measured pursuant to specifiertion 4.10.2.2, an n
everall measured F (Z) shall be obtained from a power distribution map n
and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
)
t l
SALEM - UNIT 1 3/4 2-7a Amendment No. 20 0 BD gg 3
b POWER DISTRIBUT ION Lin1TS-BASES a.
abnormal perturbations in the radial power shape, such as from rod misali gnment, ef f ect F more directly than Fg, q
b.
although rod movement' has a direct influence upon limiting FQ to within its limit, such control is not readily available to limit N
F
. and AH c.
errors in prediction for control power shape detected during startup Q y restricting ' axial flux physics test can be compensated f or in F b
N distributions. This corgensation for F is less readily bH available.
l The radial peaking f actor Fxy(z) is measured periodically to provide. assurance that the hot channel f actor, F (z), remains within its limit. The Fxy limit for Rated Thermal Power (Ffy9, as provided in the Radial Peaking Factor Limit Report per specification 6.9.1.9, was determined from expected power control manueuvers over the full range of burnup conditions in the core.
3/4 2.4 QUAIRANT 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 measurements 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 FQ is j
depleted. The limit of 1.02 was selected to provide an allowance for the j
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 correction of a dropped or misaligned rod.
In the event such action does not correct the tilt, the margin for uncertainty on Fg is reinstated by reducing the power by 3 percent f rom RATED THERMAL POWER for each percent of tilt in excess of 1.0.
l 1
SALEM - UNIT 1 B 3/4 2-5 Amendment No. 82 j
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l 7
l' POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the arameters are maintained within the normal steady state envelope of The limits are p
operation assumed in the transient and accident analyses. c demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient.
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 paraneters 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 j
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.
9 B 3/4 2-6 SALEM - UNIT 1
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