ML20147C363
| ML20147C363 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/30/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147C354 | List: |
| References | |
| NUDOCS 7812180239 | |
| Download: ML20147C363 (6) | |
Text
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UNITED STATES k
NUCLEAR REGULATORY COMMIS3 ION j.k1[Y l]
WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY 00CKET NO. 50-295_
ZION STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. OPR-39 1.
The lhclear Redulatory Ctani;sion (the Comission) has found t1at:
A.
The applici tion for amendment by Comonwealth Edison Compc 1y
- he licen ee) dated May 24, 1977 a.s supplemented September 27, 137E;, complies with the standards and requirements of the Nomic Ene"gy Act of 1954, as amenced (the Act), and the C
- mmission s rules and regulations set forth in 10 CFR C> apter I; B.
The facili:y will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
"here is clasonable assurance (i) that the activities autl orized by this anendment can be conducted without endangering th-I ealth anc safety of the public, and (ii) that such activitias will be cc 1 ducted in compliance wi th the Commission's reg ilations; I
D.
"he issuar '.e of this amendment will not be inimical to th
- omon de ense and security or to the health and saf ety o t.he publi.; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 0 the Commisston's regulations and all applicabl e requiremelts have been satisfied.
7 812180 2 M
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2.
Accordingly the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendroent and paragraph 2.C (2) of Facili*y 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 Ariendment 1
No. 40, are hereby incorpora.ad in the license.
The licensee shall operate the facility ir, accordance with the Technical Specifications.
i 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUC EAR REG'JLATORY COMMISSION
.(J//dllA A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Feactors
Attachment:
Changes to the Technical Specifications Date of Issuance: November 30, 1978 t-
ATTACHMENT TO LICENSE AMENDMENTS i
AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. OPR-39 AMENDMENT N0. 37 TO FACILITY OPERATING LICENSE NO. DPR-48 00C'tET N05. 50-295 AND 50-304 Revise Appendix A as follows:
Remove Pages Insert Revised Pages 40 40 197 197 l
198 198
7 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.2.1.B once a shift while remaining.in this condition. During heatup, theLboron concentration in the reactor coolant-loops and pressurizer shall be sampled every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The reactor coolant loop boron. concentration must not decrease by :
more than 50 ppm between successive 4
+
hour samples. The pressurizer boron C. Unit Startup concentration must not be more than 200 i
ppm less than the reactor coolant loop 1.
Insnediately prior to startup, the' boron concentration-.
reactor coolant temperature shall be
-shown to be greater than the tempera-C.
Startup
{
ture above which the noderator temp-erature coefficient is always negative 1.
The Tavg of each reactor coolant and greater than 500*F, except during loop shall be logged before low power physics tests.
attempting to bring a reactor critical.
.2.
When a reactor is approaching critica-lity, the shutdown banks shall be fully 2.
Not Applicable.
e withdrawn in sequence (shutdown bank A,B.C,0) before any other rods are j
withdrawn. The control group rods shall be no further' inserted than'the l
limits shown by Figure 3.2.2 for Unit l
1 and Figure 3.2-4 for Unit 2 for 4-loop operation and Figure 3.2 for Unit I and Figure 3.2-5 for Unit _2 for 3-loop operation when criticality is attained.
D.
Power Operation D.
Power Operation 1.
When a reactor is critical, except 1.
Rod operation shall be verified by for phvsics tests and control rod partial movement of all rods every I
exercises, the suutdown roos snoll two neew>.
Rad:.... :ch ;.as ; bee..
be fully with-exercised within the Amendment No. 40. Unit 1.
i 40 Amendment No. 37, Unit 2 j
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4 PRGPOSED TEClit:ICAL SPECIFItATION SECTION 3.9.1.6 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.9 CONTAINMENT ISOLATION SYSTEMS (per unit) 4.9 CONTAINMENT ISOLATION SYSTEM (per' unit)
Applicabil i ty:
Applicability:
Applies to containment isolation systems.
Applies to containment isolation systems.
Objective:
Objective:
To insure containment isolation within To establish the surveillance require-acceptable limits and define the operating ment for containment isolation.
3 status of the reactor containnent for plant operation.
Specification:
Specification:
1.
Isolation valve seal water system 1.
Isolation valve seal water system (Table 4.9-1)
A.
The isolation valve seal water system shall be operable unless the reactor A.
The isolation valve seal water is in the cold shutdown condition system shall be tested e"2ry except as specified in 3.9.10.
refueling outage. Performance will be acceptable if the five seal water headers are maintained at a minimum pressure of 47 psig for two hours following manual actuation. The seal water header isolation valves are closed throughout the test.
B.
The isolation valve seal water tank B.
The level and pressure of the i
shall be maintainec at a minimum isolation valve seal water tank-pressure of 68 psig and a minimum shall be checked monthly.
volume of 70 gallsas.
C.
Any one header of the isolation valve C.
Not Applicable.
seal water system nay be inoperable i
Amendment No. 40, Unit 1 for a period not to exceed four Amendment No. 37, Unit 2 consecutive days during reactor 197
, i m., + c, n.m 4,,,,
i PROPOSED.ELHrilCAL SPECIFICATI0t, SEC I~10h 2.9.2.L LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i
3.9.2.
Penetration pressurization systems 4.9 2.
Penetration pressurization systems Table 4.9-2)
A.
The penetrations (electrical and A.
The pressure of the four itrogen mechanical) and liner weld channels and penetration pressurization shall be continuously pressurized headers shall.be checked monthly, i
above 47 psig unless the reactor is i
in the cold shutdown condition except as specified in 3.9.28.
B.
Any one header of the nitrogen or D.
Immediately following maintenance air pressurization system may be on a pressurization header, the inoperable for a period not to header pressure must be checked.
exceed four consecutive days during reactor operation to permit main-tenance.
C.
The penetration air com-C.
The penetration air compressor shall-i s
pressor system and either the in-be load tested (+-10% of design strument air system or the nitrogen pressure and' capacity) during each system shall be operable except as refueling outage.
specified in 3.9.2.D.
D.
One penetration air compressor may D.
Immediately following maintenance l
be inoperable for a period not to on a penetration compressor, that j
exceed 15 days to permit compressor shall be load tested, maintenance.
E.
The upper limit for long term E.
The air finw to the penetration uncorrected air consumption fnr the pressurization headers shall penetration pressurization systems be checked monthly.
shall be less than 0.2% of the containment volume per day at 47 psig (950 SCFil).
l 198 Amendment No. 40, Unit 1 Amendment No. 37. Unit 2
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