ML19273B241
| ML19273B241 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/17/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19273B240 | List: |
| References | |
| NUDOCS 7904060017 | |
| Download: ML19273B241 (10) | |
Text
C UNITED STATES
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NUCLEAR REGULATORY COMMISSION 4
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WASHINGTON, D. C. 20555
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'\\, -A COMMONWEALTH EDISON COMPANY DOCKET NO. 503-295 ZION STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 13, 1976 as supplemented by letters dated July 14 and December 9,1977, and April 27, August 1 and 24, 1978, complies with the standards and requirements of the Atomic 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 (i) 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 yrith 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
730/IOGOO/7
. 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 License No. DPR-39 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specificatioris.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUC {AR REGULATORY COMMISSION
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A. Schwencer, Chief Operating Reactors Branch 71 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 17, 1979 es e
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UNITED STATES g
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't NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 503-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATI!JG LICENSE Amendment No. 43 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 13, 1976 as supplemented by letters dated July 14 and December 9,1977, and April 27, August 1 and 24, 1978, complies with the standards and requirements of the Atomic 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 (i) 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.
. 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 License No. DPR-48 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
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l0 (b5W A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance. March 17,1979 O
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 46 TO FACILITY OPERATING LICENSE NO. DPR-39 NjENDMENT NO. 43 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET N05. 50-295 AND 50-304 Revise Appendix A as follows:
1.
Add the following new pages 295w 295x 295y 295z 295AA 2.
Remove page iv and replace with identically numbered revised page.
8
Table of Contents (Continued)
SURVE1LI.hNCE LIMITING CONDITION FAF OPERATION REQUIREMENT PACE 3.13 Refueling Operations 4.13 243 3.13.1 Core Reactivity 4.13.1 243 3.13,2 Fuel Drop Protection 4.13.2 244 3.13.3 Containment Status 4.13.3 245 3.13.4 Radiation Monitoring 4.13.4 246 Bases 246 3.13.5 Refueling Equipment Checkout 246 3.13.6 Refueling Eauipment Operability 246 3.13.7 Spent Fuel Pit Cooling Systems 247 3.13.8 Fuel Inspection Program 3.14 Plant Radiation Monitoring 4.14 250 3.15 Auxiliary Electrical Power System 4.15 255 3.16 Environmental Radiological Monitoring Program 4.16 275 Bases 3.17.1 Ventilation 4.17.1 281 Bases 3.17.2 Aircraft Fire Detection 4.17.2 283 3.18 Steam Generator 4.18 289 Bases 3.19 Failed Fuel Monitoring 4.19 292 3.21 Fire Protection 4.21 295D l
3.22 Shock Suppressors (Snubbers) 4.22 295W 296 5.0 Design Feature 296 5.1 Site 296 5.2 Reactor Coolant System 296 5.3 Reactor Core 96 5.4 Containment System g
5.5 Fuel Storage iv Amendment No. 46, Unit 1 299 5.6 Seismic Design Amendment No. 43, Unit 2
LIMITING CCHD1TIONS FOR OPERATION SURVEILLANCE RII)UIREMENT 3.22 Shock Suppressors Snubbers) 4.22 Shock Suppressors (Snubbers)
Applicability Applicability Applies to safety related hydraulic snubbers, per Applies to safety related hydraulic snubbers, per unit.
unit.
Objective Objective To insure continued reliability of hydraulic To establish surveillanco requirements for shock suppression devices.
safety related hydraulic snubbers.
Specification Specification la. All hydraulic snubbers whose seal material 1.
During all modes of operation except cold shut- -
has been demonstrated by operating experience, down and refuel, all safety related snubbers lab testing or analysis to be compatible with as listed in station procedures shall be operabic except as noted in 3.22.2 through the operating environment shall be visually inspected in accordance with the following 3.22.4 below, schedule:
Nurber of Snubbers Found Inoperable During Inspec-tion or During Inspection Next Required Interval Inspection Interval 0,1,2 12 months 1 25%
3,4 6 months 1 25%
5,6,7,8 124 days 1 25%
9-14 62 days
+ 25%
~
15,16 31 days 1 25%
Amendmant No. 46, Unit 1 295W Amendment No. 43, Unit 2
I SilRVERI.ANCE REQUIREMENTS I IMITING conal'IloN5 FOR OPERATION 4.2e.1 The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups,
" accessible" or " inaccessible" based on their accessibility for inspection during reactor op e ra t ion. These two groups may be inspected independently according to the above schedule.
All hydraulic snubbers whose seal materials have b.
not been demonstrated to be compatibic with the operating environment shall be visually inspected for operability every 31 days.
c.
The initial inspection for accessible snubbers shall be performed within 6 months from the date of issuance of these specifications.
Inaccessible snubbers shall be inspected within 12 months from t he date of issuance of these specifications.
For the purpose of entering the schedule in Speci fi-cation 4.22.1, it shall be assumed that each unit is on a 6 month and 12 month inspection interval for accessible and inaccessibic snubbers, respectively, d.
Once each refueling cycle, a representat ive sample of at least 10 hydraulic snubbers shall be functionally tested for operability including verification of proper piston movement, lock up and bleed.
For each unit and subsequent unit found inoperable, an additional ten snubbers shall be so tested until no more failures are found or all units have been tested. Snubbers of rated capacity >50,000 lb. are exem, c from the funct ional testing. Snubbers installed in high radiation 29sX Amendment No. 46, Unit 1 Amendment No. 43, Unit 2
SURVEILI,!3CE REQUIRE 2(ENT LIMITING CONDITION FOR PERATION areas or in especially difficult to remove locations need not be selected for functional tests provided operability,,was previously verified.
2.
Not applicable 2.
From and after the time that a hydraulic snubber is determined to be inoperable, continued reactor operation is permissible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner made operable.
3.
If the requirements of 3.22.1 and 3.22.2 cannot be 3.
Not applicable met the reactor shall be brought to the hot shut-down conditions within four hours.
After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the hot shutdown cendition if the snubber is not operable the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
If a snubber is determined to be inoperable while 4.
Not applicable the reactor is in the shutdown or refuel mode, the snubber shall be made opetable or replaced prior to reactor startup.
5.
Snubbers which are applicable to the requirements of 3.22 and 4.22 will be listed and maintained in station procedures.
295Y Amendment No. 46, Unit 1 Amendment No. 43, Unit 2
pues :
3.22 & 4.22 Snubbers are designed to prevent unrestrained failures.
The number of ir. operable pipe motion under dynamic loads as might occur snubbers found during a required inspection
~
during an earthquake or, for some snubbers, severe determines the time interval for the transients, while allowing normal thermal motion next required insperLion.
Inspectior.s during startup and shutdown..The consequences of performed before that interval has elapsed an inoperabic snubber is an increase in the may be used as a new reference point probability of structural damage to piping as a to determine the next inspection, result of a seismic event or, for some snubbers, liowever, the results of such early other events initiating dynamic loads.
It is inspectior.s performed before the original therefore required that all snubbers required to required time interval has elapsed protect tne primary coolant system or any other
( nom i r.a l time less 2S%) may not safety system cr component be operable during be used to 1cnqthen the required innoc etion reactor operation.
interval.
Any inspection whose result.s require a shorter inspection interval Decause the snubber protection is required will override the previous schedule.
only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
In case a shutdown is required, the allowance of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reach a hot shutdown condition will pennit an orderly shutdown consistent with standard operating procedures. After a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in hot shutdown, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to reach cold shutdown conditions. Since plant To further increase the assurance startup should not comence with knowingly of snubber reliability, functional defective safety-related equipment, Specification tests should be perforned o ce each 3.22.4 prohibits startup with inoperable snubbers.
refueling cycle.
These teste will include stroking of the snubbers to verify proper piston movenent, lockup and bleed.
Ten snubbers represents an adequate sample for such tests.
Observed failures on these san,ples should require testina All safety related hydraulic snubbers are visual ~ y inspected for overall integrity and of additional units.
To minimize personnel operability.
The inspection will include verifica-exposures, snubbers installed in hich tion of proper orientation, adequate hydraulic radiation zones during reactor shutdown or in fluid level and proper attachment of snebber to especially difficult to remove locations may be piping and structures.
exempted frem these functional testing requirements provided the operability of those snubbers was The inspection frequency is based upon maintaining demonstrated during functional testing at either a constant level of snubber protection. Thus the required the completion of their fabrication or at a inspection interval varies inversely with the observed subsequent date.
Snubbers of rated capacity of snubber 50,000 lb. or greater are exempt from the functional 295g Amendment No. 46, Unit 1 Amendment No. 43, Unit Z
Bases:
3.22 & 4.22 (Continued) testing requirements because of the impracticability of testing such large units.
Experience at operating facilities has shown Snubbers may be added to safety related that the required surveillance program should assure systems provided they are added to station an acceptable level of snubber perfermance provided procedures and documented in accordance with that the seal materials are compatible with the 10 CFR 50.59.
operating environment.
Snubbers containing seal material which has not been demonstrated by operating experience, lab tests or analysis to be compatible with the operating environment should be inspected more frequently (every month) until material compati-bility is confinned or an appropriate changeout is completed.
Examination of defective snubbers at reactor facilities and material tests performed at several laboratories (Reference 1) has shown that millable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many snubber locations. Although molded polyurethene exhibits greater resistence to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the molded polyurethane. Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene.
) Report 1. R. Erickson, Bergen Paterson to K. R. Goller, NRC, October 7,1974 295AA Amendment No. 46 Amendment No. 43, Unit 1
, Unit 2