ML20010E576
| ML20010E576 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/20/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20010E575 | List: |
| References | |
| NUDOCS 8109040285 | |
| Download: ML20010E576 (6) | |
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o UNITED STATES
[ ' * ; y,( 'i NUCLEAR REGULATORY COMMISSION 3.' '
s W ASHING TON, O. C. 20555
- s%, u j PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLE *~. PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-1 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated June 29, 1981 complies with the standards and requirements of the 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 41 of the Commission's regulations and all applicable requirements have been satisfied.
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l 8109040285 810820 i
PDR ADOCK 05000344 p
' 9 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 Operating License No. NPF-1 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except as noted in paragraph 2.C.(10) through 2.C.(12) below.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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V y Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
August 20, 1981 I
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 65 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-37 3/4 7-37 3/4 7-38 3/4 7-38 3/4 7-39 I
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PLANT SYSTEM $
0 3/4.7.11 CONTROL BUILDING MODIFICATION CONNECTION BOLTS
- LIMITING CONDITION FOR OPERATION 3.7.11 The structural adequacy of the through-wall bolts used to tie rein-forced concrete and steel plate to the Control Building west and east walls shall be maintained at a level consistent with the acceptance criteria in Specification 4.7.11.1.
APPLICABILITY:
ALL MODES ACTION:
a.
With the structural adeouacy of the bolts not conforming to the above requirements, restore the structural adecuacy of the bolts to within the limits within 14 days.
b.
If the structural adequacy of the bolts does not conform to the above requirements, report the degradation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and prepare and submit a special report pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the degradation and plans 'for restoring the structural adequacy of the bolts.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS l
4.7.11.1 The structural adequacy of the through-wall bolts used to tie rein-forced concrete arJ steel plate to the Control Building west and east walls shall be demonstrated at the end cf 6 months and 1, 3 and 5 years af ter l
initial tensiosing and at 5-year intervals thereaf ter. Structural adequacy l
of the bolts shall be demonstrated by:
l a.
Demonstrating that each bolt in a random and representative sample of not less than 25 percent of the total number of bolts has a tension equal to or greater than 80 percent of the initial bolt tension.
If the tension in any bolt is below 80 percent of the initial bolt tension, the tension in two adjacent bolts shall be measured.
If either of these bolts is found to have less than 80 percent of the initial bolt tension, then all bolts shall be tested.
All bolts found to have less than 80 percent of the initial bolt tension shall be retensioned to the original installation tension value.
- lhis Technical Specification shall become effective upon initial tensioning of the connection bol ts.
l TROJAN-UNIT 1 3/4 7-37 Amendment No. 47,65 l
PLANT SYSTEMS o
SURVEILLANCE REQUIREMENTS (Continued)
Demonstrating the acceptability of each test sample by b.
showing that i-2e is greater than 0.8X, where i is the o
mean tension for that sample, o is the standard deviation, is the initial bolt tension.
If this criterion is and X not met, then all bolts shall be tested to the criteria in o
If the mean sample tension i is below 0.8Xo, the (a) above.
circumstances shall be reported pursuant to Technical Specification 6.9.1.8.1.
Determining that there is no evidence of degradation or a'onormal conditions by visual inspection while under tension c.
for those bolts which are not removed of the condition of all bolts in the sample, their end anchorages and concrete In addition, or masonry in th? vicinity of the anchorage.
total number of bolts in the walls shall be 10 percent of the removed and examined by a surface examination technique for evidence of cracks or other abnormal degradation.
The grease for these shall also be checked for presence, consistency, appearance and to assure that it is within its specification limits for water content.
If cracks or degradation are dis-covered in any one bolt (including condition of grease), two If adjacent bolts (including grease) shall be examined.
cracking or degradation is discovered in either of these two, then all bolts shall be examined.
Defective bolts or grease Abnormal degradation of the bolt or grease shall be replaced.
shall be reported pursuant.to Technical Specification 6.9.1.8.i.
I If the bolts inspected during the first four inspections meet d.
the acceptance criteria of (b) and (c), then the sample for the subsequent inspections may be reduced to not less than 10 per-cent of the total number of bolts in the walls for the testing required by Paragraph (a) and not less than 5 percent of the total number of bolts in the walls for that required by Para-i graph (c).
Beginning with the third year inspection, a trend analysis e.
shall be used to predict the existing balt tension at the end of the next inspection interval (2 years or 5 years thereaf ter).
If the predicted bolt tension is below.75 of the initial bolt tension (i-2a <.75Xo), this shall be considered as abnormal degradation and reported pursuant to Technical Specification 6.9.1.8.1.
A detailed report of any abnormal degradation [as defined f.
in (b), (c) and (e) above) shall be submitted pursuant to Technical Specification 6.9.2 within 90 days af ter completion of the surveillance testing.
i TROJ AN-UNIT 1 3/4 7-38 Amendment No. /7, 65
PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.7.11.2 To assure that the surveillance intervals for the first three inspections in Specification 4.7.11.1 are sufficient to maintain mean bolt tension above.75 of the initial bolt tension, the tension in a special sample group of 10 bolts (six in the west wall and four in the east wall-) shall be measuret at 3-month intervals from initial tensioning. The tension values for the bolts in this special sample group shall be used to determine the pattern of reduction in initial tension with time due to bolt relaxation and shrink /
creep of the concrete and grout.
Surveillance of the tension in this special sample group of bolts shall continue until tension reductions have stabilized or until the third year at which time the trend analysis of Specifica-tion 4.7.11.1.e shall govern.
If tension in any bolt in the special sample group falls below.8 of initial bolt tension, the circumstances shall be reported pursuant to Specification 6.9.1.8.f.
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rROJAN-UNIT 1 3/4 7-39 Amendment.No. J7, 65
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