ML20070K223
| ML20070K223 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/21/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K225 | List: |
| References | |
| TASK-03-07.C, TASK-05-10.B, TASK-05-11.A, TASK-3-7.C, TASK-5-10.B, TASK-5-11.A, TASK-RR NUDOCS 8212300038 | |
| Download: ML20070K223 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION O
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C0NSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 72 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications (3) for amendment by Consumers Power Company (the licensee) dated July 29, 1982 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended I
(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. applications, the provisions of the Act, and the rules and regulations of the Commission; j
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the i
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 a.id all applicable requirements have been satisfied.
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8212300038 821221 PDR ADOCK 05000255 p
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, 2.
Accordingly, the license is amended by, changes to the Technical Specifications as indicated in the attachment tc this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B (Environmental Protection Plan), as revised through Amendment.No. 72, 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
.y Dennis M. Crutchfiel, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 21, 1982 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 72 PROVISIONAL OPERATING LICENSE N0. DPR-20 DOCKET NO. 50-255 Revised Appendix A Technical Specifications by removing the following
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pages and by inserting the enclosed pages.
The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
y Remove Pages Insert Pages
.c 3-25a 3-25a
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s 4-17 4-17*
4-18 4-18
-s, 4-18a
,t 4-32a j,
I 4-38 4-38
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3.1.8-
-Overpressure Protection Systems Specifications s
a.
When the temperatuge o"f one or more of the primary coolant system.
'f cold legs is g 250 F, or whenever the shutdown cooling isolation valves (MOV-3015 and MOV-3016) are open, two power operated relief valves (PORVs) with a lift setting of f 00 psia, 4
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or a reactor coolant system vent of 31.3 square inches shall be.
operable except as specified below:
(1) With one PORV inoperable, either restore the inoperable
'PORY to operable status within 7 days or depressurize and N8.
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vent the PCS through a.> 1.3 square inch vent (s) within 7
the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the PCS in a vented condition
(2) With both PORVs inoperable, depressurize and vent the PCS through a 31.3 square inch vent (s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the PCS in a vented condition until both PORVs have been restored to operable status.
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b.
In the event either the PORVs or the PCS vent (s) are used to mitigate a PCS pressure transient, a Special Report shall be prepared and suixnitted to the Commission within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient and any corrective action necessary to prevent recurrence.
Basis The OPERABILITY of two PORVs or an PCS vent opening of greater than 14 square inches ensures that the PCS will be protected from pressure transients which could exceed the limits of Appgndix G to 10 CFR Part 50 when one or more of the PCS cold legs are g 250 F.
Either PORV has adequate relieving capability to protect the PCS from overpressurization when the transient is limited to either (1) the start of an idle PCP with the secondard water temperature of the steam generator 4 70 F above the PCS cold leg temperatures'or (2))the start of a HPSI, pump and its
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injection into a water solid PCS. (1 Whenev'er the SCS is not isolated from the reactor' coolant system, the PCS will be vented or the PORVs vill be in service. This require-ment will ensure that the overpressurization of the SCS that could lead to a loss-of-coolant accident outside containment is prevented.
References (1) " Palisades Plant Overpressurization Analysis," June,197 ( and
" Palisades Plant Primary Coolant System Overpressurization Sub-system Description," October, 1977 (2) Systematic Evaluation Program Topic V-10.B NRC letters to the licensee transmitting the final topic evaluation dated October 27 and. December 23, 1981.
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3-25a Amendment No. jf 72 i
inspection techniques that have been proven practical, and the conclusions of the evaluation shall be used as appropriate to update the inspection program.
s, f.
Surveillance of the regenerative heat exchanger and primary coolant pump flywheels shall be performed as indicated in Table 4.3.2.
g.
A' surveillance program to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR.
The specimen removal schedule shall be as indicated in Table 4.3.3.
h.
Periodic leakage testing (a), (b) on each check valve' listed in Table 4.3.1 siiall be ' accomplished prior to returning to the Power Operation Condition af ter every time the plant has been -
placed in the Refueling Shutdown Condition, or the Cold Shutdown Condition for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if such testing has not been accomplished within the previous 9 months, and prior to returning t
the check valves to service after maintenance, repair or replace-ment work is performed on the valves.
1.
Whenever integrity of a pressure isolation valve listed in Table 4.3.1 cannot be demonstrat,ed.and credit ' s being tal<en for
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i 4-17 Amendment No.
72
( HRC Order dated April 20,1981 )
(a)To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.
( ) Reduced pressure. testing is acceptab'ie (see footnote 5 to Table 4.3.1).
Minimum test differential pressure shall not be less than 150 psid.
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compliance with Specification 3.3.3.b, the integrity of the remaining check valve in each highepressure line having a leaking valve shall be determined and recorded daily and the position of the other closed valve located in that pressure line shall be recorded daily.
h.3.J. Following each use of the LPSI system for shutdown cooling, the reactor shall not be made critical until the LPSI check valves (CK-3103, CK-3118, CK-3133 and CK-3148) have been verified closed.
Basis The inspection program specified places major e=phasis on the areas of highest stress concentration as determined by general design evaluation and experience with similar systems.(1 In addition, that portion of the reactor vessel shell velds which vill be subjected to a fast neutron dose sufficient to change ductility properties vill be inspected. The inspections will rely primarily on ultrasonic methods' utilizing up-to-date analyzing equipment and trained personnel. Pre-operational inspections will establish base conditions by determining indications that might occur from geo=etrical or metallurgical sources and frem discontinuities in veldments or plates which might cause undue concern on a postservice inspection. To the extent applicable, based upon the existing design and construction of the plant, the
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requirements of Section XI of the Code shall be complied with.
Significant exceptions are detailed in the requests for relief which have received NRC approval and are contained in the Class 1, Class 2 and Class 3 Long-Term Inspect.on Plans.
4-18 l
Amerdment No.,&T 72
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.a Reactor Vessel Surveillance Specimens Table h.3.3 is consistent with the surveillance program as presented in the FSAR.( }
However, the withdrawal schedule has been modified to reflect the slightly different vall fluence values resulting from removal of the thermal shield.
Valve Testing To ensure the continued integrity of selected check valves which are relied upon to preclude a potential LOCA outside containment, special requirements for periodic leek tests are specified.
In addition a valve disk position check for the LPSI check valves is specified following each use of the LPSI system for shutdown cooling. This
' position check ensures that the four LPSI check valves have reclosed upon cessation of shutdown cooling flow.
References (1) FSAR, Section h.5.6 (2) FSAR, Section h.5 3 (3)
Systematic Evaluation Program Topic V-11.A, NRC letter to the licensee transmitting the final topic evaluation dated
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November 9,1981 i
x, 4-18a Amendment No. g 72
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k.5 CONTAINMENT TESTS -(Con't) i h.5.8 Dcue Delamination Surveillance If, as a result of a prestressing system inspection under Section 4.5.h, corrective retensioning of five percent (8) or more of the total number of dome tendons is necessary to restore their liftoff force: te within the limits of Specification 4.5.h, a dome delamination l
inspection shall be performed within 90 days following such l
corrective retensioning. The results of this inspection shall be reported to the NRC.
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l Amenda. ant No. 72 h-32a
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4.5 CONTAINMENT TESTS (Con't) two weeks (in extreme weather) during this two-year period, e,
a visual inspection shall be made for stress indications.-
After this time, if no unexpected behavior of the liner plate or penetration assemblies is observed, the surveillance program i
will be extended at that time.
Containment dome delamination inspections performed in 1970 and 1982 have confirmed-that no concrete delamination has occurred.
The possibility that delamination might occur in the future is remote because dome tendon prestress forces gradually diminish through normal tendon relaxation and concrete strength normally increases over time. To account for this remote possibility, however, an additional delaminiation inspection will be perfomed in the event that 5% or more of the installed tendons must be retensioned to compensate for excessive' loss of prestress. This inspection would be to confirm that any systematic excessive prestress loss did not result fras delamination and that the retensioning process did not result in delamination.
References (1) FSAR, Section 5.1.2.
(2) FSAR, Section 5 1.8.
(3) FSAR, Section 1k.22.
(4) FSAR, Section 8.5.k.
(5) FSAR, Section 6.2.3 (6) FSAR, Section 5 1.8.k.
(T) FSAR, Amendment No. 1k, Question 5.37 (8) 10 CFR Part 50, Appendix J.
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Cha19e No./
k-38 Amendment No. 72
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