ML20206D927
| ML20206D927 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/14/1988 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206D931 | List: |
| References | |
| NUDOCS 8811170328 | |
| Download: ML20206D927 (4) | |
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UMTt3 sTATa8 NUCLEAR REGULATORY COMMIS$10N E
a WASHING TON. D. C. 30006 e
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CONSUMERS POWER COMPANY t
PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PR0VIS!0NAL OPERATING LICENSE Amendamnt No,116 License No. LPR-20 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
F A.
The application for amendment by Consumers Power Company (the ifcensee) dated August 4, 1988, as supplemented October 4, 1988, complies with the star >dards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i
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 commoh 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 I
of the Commission's regulations and all applicable requirements have i
betn satisfied.
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SS11170328 S31114 l
PDR ADOCK 0500025*.
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2.
Accordingly, the license is amended by changes to the Technical Specificaticns as indicated in the attachment to this license asentiment and Paragraph 3.8. of Provit lonal Operating License
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No. OPR-20 is hereby amended to read as follows, t
Technical Specifications i
The Technical Specifications contained in Appendices A and B, I
as revised through Amendment No.116, are hereby incorporated i
I in the license.
The ifcensee shall operate the facility l
in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY ComIS$10N i
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,kinbtL-w; i
Theodore Quay, Acting Director j
Project Directorate III-1 Division of Reactor Projects - III, IV, V i
& Special Projects
Attachment:
I Changes to the Technical Specifications Date of Issuance: November 14, 1988 i
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ATTACHWEN1 Ta LICENSE AMENOMENT NO. 116 PJVISIONAl.OPERATINGLICENSENO.OPR-20 DOCKET NQ. 50-255 Revise the Appendix A Technical Specifications by removing the page identified below and inserting the attached page.
The revised page is identified by the captioned amendment number and contains marginal lines indicating the areas of change.
REMOVE INSERT 3 25 3-25 e
j.1 PRIMARY _ COOLANT SYSTEM (Contd) 3.1.7 Primary and Secondary Safety Valves Spe2ificagons
- a. The rm: Lor shall not be made critical unless all three r
.s, wizer safety valves are operable with their lift of
'naintained between 2500 psia and 2580 psia (i 1%).
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a of one operable safety valve shall be installed on o,
.urizer whenever the reactor head is on the vessel.
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the reactor is in power operation, a minimum of andary system safety valves shall be operable with their settings between 985 psig (1 30 psig) and 1025 (i 3%) psig.
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Basis The primary and secondary safety valves pass sufficient steam to limit the primary system pressure to 110 percent of design (2750 psia) following a complete loss of turbine generator g
load without simultaneous reactor trip while operating at 2650 W.g) g The reactor is assumed to trip on a "High Primary Coolant System Pressure" s1gnal. To determine the maximum steam flow, the only other pressure relieving system assumed operational is the i
secondary system safety valves. Conservative values for all system parameters, delay times and core moderator coefficient are assumed. Overpressure protection is provided to the portions of the primary coolant system which are at the highest pressure considering pump head, flow pressure drops and elevation heads.
If no residual heat were removed by any of the means available, the amount of steam which could be generated at safety valve lift pressure would be less than half of one valve's capacity. One valve, therefore, provides adequate defense against overpres-i surization when the reactor is suberitical.
Thetotalre}iefcapacityof.e24secondarysystemsafetyvalves is 11. 7 x 10' lb/h. This is based on a steam flow equivalent to an NSSS power level of 2650 W, at the nominal 1000 psia valve lif t pressure.
At the power rating of 2530 W, a relief capacity of less than g
0 11.2 x 10 lb/h is required to prevent overprest.urization of the i.
secondary system of losa, of load conditions, ani 23 valves provide relieving capability of 11.2 x 40 lb/h.(1,2) 6 The overpressurization analysis for the loss of load event (2) j supports the specified secondary safety valve lift press 6te
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tolerance. ASME B&PV Code, 1986 edition,Section XI, subsection
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IW-3500 specifies ANSI /ASME OM-1-1981 requirements which
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allow the specified tolerances in the lift pressures of the
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safety valves.
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References (1) FSAR Sections 4.3.4 and 4.3.7.
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(2) ANT-87-150(NP) Volume 2, Section 15.2.1.
Amendment No M. M 6 3-25
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