ML20080F124
| ML20080F124 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/24/1984 |
| From: | Rooney V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080F127 | List: |
| References | |
| NUDOCS 8402100335 | |
| Download: ML20080F124 (7) | |
Text
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'g UNITED STATES
[ l'y [ y i NUCLEAR REGULATORY COMMISSION 4
WASHINGTON, D. C. 20555
>o e COMMONWEALTH EDISCN COMPANY AND
)
IOWA-ILLIFOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00A0 CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. OPP-30 1.
The Nuclear Pegulatory Comission (the Commission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated July 5 and July li., 1983, comply 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission'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 isr.uance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all a9plicable reauirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attach.nent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-30 is hereby amended to read as follows:
8402100335 840124 PDR ADOCK 05000265 P
1
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the l
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.
FOR THE NUCLEAR REGULATORY COMMISSION 17
=,
Vernon L. Rooney,l Acting Chief Operating Deactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 24, 1984 t
9 l
L
ATTACHMENT TO LICENSE AMENDPENT NO. 80 FACILITY OPERATING LICENSE NO. OPR-30 DOCKET NO. 50-265 Revise the Appendix "A" Technical Specificatiers as follows:
Remove Replace 1.2/2.2-1 1.2/2.2-1 3.5/4.5-10 3.5/4.5-10 Fig. 3.5-1, Sheet 3 Fia. 3.5-1, Sheet 3 3.5/4.6-4 3.6/4.6-4 4
5 r
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QUAD-CITIES DPR-30
( i 1.2/2.1 REACTOR COOLANT SYSTEM SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING Applicability:
Applicabilityt Applies to limits on reactor coolant' system Applies to. trip settings of the instruments and pressure.
devices which are provided to prevent the reactor system safety limits from being exceeded.
Objective:
Objectiv'et To establish a limit below which the integrity of the To derme the level of the process variables at which reactor coolant system is not threatened due to an automatic protective action is initiated to prevent overpressure condition.
the safety limits from being exceeded.
SPECIFICATIONS A. ime reactor coolest system prwaere as aumered A.
Reactor coolant high-pressure scram shall be btemve.1stemspee.prweeresaatoster s1060 P55 -
l not emoose 1Ms pass at say tame unsa 8
1rradiated fuel is present la the reester veneel.
B.
Primary system safety valve nominal settings shall be as follows:
1 velve me 1135 peig l
2 velves at 1240 psig 2 valves at 1250 psig 4 valves at 1260 psig "rrarget Rock combination safety /rehef valve The allowahle setpoint error for each valve shall be i1%
l l
l l
l t
1.2/2.2-1 AMENNENT No. % p', 80 l
l
Quad Cities OPR-30 within the prescribed limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall De brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
Maximum allowable LHGR for all 8X8 fuel types is 13.4 KW/ft.*
j i
K.
Minimum Critical Power Ratio (MCPR)
K.
Minimum Critical Power (MCPR)
During steady-state operation at rated The MCPR shall be determined daily during core flow, MCPR shall be greater than steady-state power operation above 25%
or equal to:
of rated thermal power.
1.34for%ye4.0.73 secs 1.39 for f73ye 2 0.86 secs 0.385 7a've + 1.059 for 0.73< Tave 4. 0.86 secs where.7 ave = mean 20% s' cram insertion time for all surveillance.
data from Specifi;:ation 4.3.C which has been gene-ratet* in the current cycle.
For core flows other than rated, these nominal values of MCPR shall be increased by a factor of kr whare kr is as shown in Figure 3.5.2.
If any time during operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribad limits.
If the steady-state MCPR is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.
o For the purpose of the end-of-cycle 6 Barrier Fuel Ramp Test, the steady-state LHGR for j
the Barrier Ramp Cell fuel may exceed the maximum allowable LHGR identified in Technical l
Specification 3.5.J by no more than 10 percent (14.7 KW/ft), effective from initiation of the test until the end of operation Cycle 6 shutdown.
Amendment No. pI, f, 7/, 80 3.5/4.5-10 6312N O
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Amendment No. 5.4, 80
- _ - -. _ =
i j
QUAD-CTIES DPR-30
- 2. Both the sump and air sampling sys.
tems shall be operable during rearsor power opration. From and aAer the date that one of these systems is stade or four d to be inoptable for any rua.
son. reactor power operation is per.
missible only during the sexeeding 7 days.
f
- 3. If the eseditions in I or 2 above can.
act be met. an orderly shutdown shall be initiated and the reactor shall be in a sold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Sefer) med Relief Yalva E.
Sarery and Relief Yalves
- 1. Prior to nacor startup for power op.
A minimum of 1/2 of all safety valves shall be esaiion. during reactor power operat.
bench checked or replaced with a bench ing conditions. and whenever the reac.
tot coolant pressure is greater than 90 checked valve each refueling outage. The pop.
ping point of the sarety valves shall be set as pig and temperature greater than follows:
320' F. all nine of the safety valves shall be oprable. The solenoid.
Number of Yahrs Serpeent (psig) activated pressure valves shall be oper.
able as required by Specincation '
I 1135"'
l 3.3.D.
2 IN 2
12$0
- 2. If Sperincation 3.6 E.1 is not met. the 4
1260 nactor sha!! remain shut down until the condstion is corrected or, if in The allowable setpoint error for each vaive is operation, an orderly shutdown shall i1%
be initiated and the reactor coolant pressure and temprature shall be A!! relief valves shall be cheened for set Pres.
below 90 psig and 320' F within 24 sun asch nfuehg outage. N art prussuns shall be:
Number of Yaher Serpens (psog)
I sil3Sai 2'
sil15 2
51135
"' Target Rock sombination marery/ relief valve.
F.
Sewarallaesgrity F.
Sensenwellnesytey The structural hteytty of the.prirnary system The mondestructive hapetises hsted in Table boundary sad be mentained at te level so.
d.61 shad be prformed as spesified he asser.
quired by the ASME Boiler and Freemre Vesert danes with Secties XI of the ASME SoGet and Code.Section XI " Rules for leurvier Inspeedes Pressus Yeaal Code,1971 Edities. Sunener of Nuclear Power Plant Components",1974 1971 Addeeds. The rensha obtained from som.
Ednma. Senmer 1975 Addeada (ASME Code phaner wfth this speelflatise we be eveheated soeuse xt).
aner 5 years and the chw.oas we tw mwwed with the NRC.
Amendment No.
80
,n
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