ML20091F203
| ML20091F203 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/27/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20091F206 | List: |
| References | |
| GL-91-01, GL-91-1, NUDOCS 9204200222 | |
| Download: ML20091F203 (6) | |
Text
.
p* *t sn
/
Ir.
UNITID STATES
!A.,. f %
NUCLE AR REGULATORY COMMISSION i i
/f wAsamotoN.o c. tom s ?.
L:. / a gt *f
- ...+
t GMyMERS POWER COMPANY DOCKET NO. 50-255 j
U PALISADES PLANT AMENDMENT TO FAClllTY OPERATING LJIIM[
Amendment No. 142 License No. DPR-20 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated November 12, 1991, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc the Comission's rules and regulations set forth in 10 CFR Chapter I; 9
P.
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 (i) that the act1vities 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; 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 the license amendment and Paragraph 2.C.2 of facility Operating License No. OPR-20 is hereby amended to read as follows:
t 9204200222 920327 ADOCKOD00g5 DR u
ltilLdal Spetif.itg11t!11 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142 are hereby incorporated in the license.
The licensee shall tverate the facility in accordance with the Technical Spacifications.
3.
This license amendment is effective as of its dat, of issuance.
FOR THE NUCLEAR REGULA7ORY COMMISSION L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 27, 1992 i
l 4
\\
IJ1A0iMEtil To LImtit AMmDE0J0JR
[Aml1Y OPERAIMLLICt!6t fiQ. OPR-20 DOMLIl0m W-ZH Revise Appendix A Technicci Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identifie! by the amendment nun.ber and contain marginal lines indicating the area of change.
ElliQ1l 1111B1 4-16 4-16 4-18 4-18 4-23 4-23
t-4.3 SYSTEMS StlRVElttANCE APPLICABILJ1Y Applies to preoperational and inservice structural surveillance of the reactor vessel and other Class 1. Class 2 and Class 3 system components.
OBJECTIVE To insure the integrity of the Class 1 Class 2 and Class 3 piping systems and components.
SPECIFICATIONS a,b,c d Deleted e.
The Inservira inspection program shall be reevaluated as required by 10 'CFR 50, section 50.55a(g)(5) to consider incorporation of new inspection techniques that have been proven ptactical, and the conclusions of the evaluation shall be used as appropriate to update the inspection program, 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.
)
4-16 Amendment No.D, U 4, 142 l
4 4.3 SYSTEMS SURVElllAE { (Cont'd)
EA111 The inspection program specified places major emphasis on the areas of highest stress concentration as determined by general design evaluation and experience with similar systems.0)
In addition.
1 that portion of the reactor vessel shell welds which will be subjected to a f ast neutron dose sufficient to change ductility properties will be i
inspected.
The inspections will rely primarily on ultrasonic methods i
utilizing up-to date analyzing equipment and trained personnel.
Presperational inspections will establish base conditions by determining i
indications that might occur from geometrical or metallurgical sources and from discontinuities in weldments or plates which might cause undue concern on a postservice inspection. To the extent applicable, based upon the exi!, ting design and construction of the plant, the 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 1
are contained in the Class 1, Class 2 and Class 3 Long Term Inspection Plans.
Valve _Testina lo ensure the_ continued integrity of selected check valves which are relied upon to preclude a potential LOCA outside containment, special requirements for periodic leak tests are specified.
In addition a valve disk position check for the LPSI check valves is specified 4110 wing 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.
Ephrence s (1)
FSAR, Section 4.5.6 i
(2)
Deleted l
l (3)
Systematic Evaluation Program Topic V-II. A.
NRC letter to the licensee transmitting the final tepic evaluation dated November 9 1981.
j L
4-18 Amendment No. EJ, 72, 170, 141
._ -. _ _ _ _ _ _. _.. _. _.... _ _ _ _. _ _ _ _ _ _ _.. _ _ _...... _ -. ~ _ _.,. _ _
i TABLE 4.3.2 Miscellaneous Surveillance items i
. __JM,pme n t Method frequency i
1.
Regenerativo Heat Exchanger
- a. Primary Side Shell to Volumetric 5 Year Maximum Tube Sheet Welds Interval (100%)
- b. Primary Head Volumetric 5 Year Maximum Interval (100%)
2.
Primary Coola6 Pump Volumetric 100% Upper Flywheel Flywheelt Ea:h Refueling t
4 23 Amendment No. Jf, 79,142
... - ~. -
~. -. - -
~
.