ML20055E674
| ML20055E674 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/28/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055E675 | List: |
| References | |
| NUDOCS 9007120221 | |
| Download: ML20055E674 (5) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION y'
WASHINGTON, D. C. 20666 o
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CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 y
AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.
132' License No. -DPR-20
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1.
The Nuclear Regulatory Commission (the Consnission)-has found that:
A.
The application for amendment by Consumers Power Company-(the licensee) dated March 6,,1990, and supplemented June 21, 1990, complies with the standards and requirements of the Atomic Energy 4
Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in.10 CFR Chapter I; 8.
The facility will o)erate in conformity with the application,
.the provisions of tie Act, and the rules'and regulations of the Commission; 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 (li) that such activities will be 3
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will net 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.-
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9007120221 900628 M
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.Accordingly,-the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
,l Technical Specifications l
i The Technical Specifications contained in Appendices A and B, i"
as revised through Amendment No.132, 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 l
and shall be implemented not later than_ July 4, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION I
h -C. ha Robert C. Pierson, Acting Director s
Project Directorate III-1 Division of Reactor Projects - III, l
IV, V & Special Projects l
Office of Nuclear Reactor Regulation
Attachment:
' Changes to the Technical o
L Specifications L
Date of Issuance: June 28, 1990 L
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.,y-ATTACHMENT TO LICENSE AMENDMENT _NO. 132 PROy_IS10HAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 "r
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' Revise-AppendixATechnicalS>ecificationsbyremovinglthepage;ide'ntified below and inserting the attacled page. The revised page is identified by the captioned amendment number and contain marginal lines indicating the area of
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REMOVE INSERT 4-68 4-68
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4-68a 4-68a a
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' Ausmented Inservice inspection Proarsa. for Stesa Generators Applicability Applies to the tubes within both steas. generators.
Ob.iective To provide assurance of continued intearity of the steam generator
. tubes over their service lifetime.
spoeiftestion 4.14.1 Inspection Interval Inspections will be performed at an in months after the previous inspection.* g al of up to 24 calendar Additional tube inspections shall be performed when primary to secondary leakage g
(not including leaks originating from tube to tube sheet welds) enceeds the leakage limits delineated in Specification 3.1.5d.
4.14.2 Inspection Requirements 4.14.2.1 For the purposes of this specifiention, " tube" refers to that portion of the steam generator tubing from the point of entry on the cold leg side to the top support of the cold leg, or from the point of entry on the hot leg side to the top supp. ort of the cold leg.
4.14.2.2 Tubes requiring inopoocion will ineludo all unplugged subec with eddy current indications of tube wall degradation greater than or equal to 30% in either of the previous, two inspections. Limited access tubes subject to this requireatnt, which result in
.significant added radiation exposure to inspect, shall be iuspected during an interval not to exceed two ccnsecutive inspectione.
4.14.2.1 Tubes requiring inspection will also include a random sample of 2%'of the hot leg tubes and 1% of the cold leg tubes in each steam generator. Random samples shall be drawn frca those unplugged Lubwe that du uut beve tube =m11 depedwLivu 14 utif1=J as greater than or equal to 30% during the previous two inspections.
- The interval may be extended to 30 monthe if the mean degradation incrosse for the previous steam generator inspection interval was less than +12.
A one-time exception is allowed from the periodic eddy castrent inspection due by July 4,1990. This exception is valid. for a limited time up to the September 1990 refueling outage when the steam generators are scheduled to be replaced. If for any reason the steam generators are not replaced, the required inspections of Technical Speedfication 4.14 shall be completed prior to startup from the 1990 refueling outage.
4-68 Amendment No. 33. 52, 19(, 112, 132 l
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4.14.2.4 A baseline inspection of all newly installed' sleeves shall be performed prior to plant operation. Inspection of each installed I
sleeve shall be performed once per three steam senerator tube 1
inspection intervals, with approzinately one-third of the sleeves inspected during each inspection interval.** In the event of sleeve degradation the sleeve inspection interval shall be evaluated.
4.14.2.5 In the case where a tube is sufficiently restricted to prevent passage of an 0.540-inch diameter., probe (blocked). 'all unpluaaed
.j tubes surrounding the blocked. tube will be saused to ensure acceptable denting levels.
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4.14.2.6 In the event that tube inspections are required due to primary to secondary _leakate, a'6% sample of unplunged tubes in the affected t
leg (s)-in each steam senerator with leakane in violation of the limits of Specification 3.1.5d shall be inspected.
4.14.3 Supplementarv Sampling Raoutrements-4.14.3.1 If the inspection pursuant to 4.14.2.2 and 4.14.2.3 or 4.14.2.6 vields results that exceed one or more of the following criteria.
4 then additional samples of unpluased tubes shall be inspected accordina to Figure 4.14.1.
a)
More than 10% of the inspected tubes in a les have detectable wall degradetion (greater than or equal to 30% through wall)
-where no previous degradation was detected.
b)
More than 10% of the inspected tubes in a leg exhibit further wall degradation (greater than a 10% increase in through wall degradation).
L c)
More than 1% of 'the inspected tubes in a leg have indications lL of tube wall degradation in excess of the repair criteria of Specification 4.14.4 where no wall degradation greater than 30% was detected in the previous two inspections.
I 4.14.3.2 In the event that any of the above linits are exceeded, prompt I
notification to the Nuclear Regulatory Commission pursuant to 10 CFR 50.72 shall occur.
Inspection of the installed sleevan darSR the inspection beginning in December 1987 is not required.
1-68a AmendmentNo.39.Jf.))f,132
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