ML20070H280
| ML20070H280 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/14/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20070H284 | List: |
| References | |
| DPR-50-A-187 NUDOCS 9407210186 | |
| Download: ML20070H280 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556 4001 METROPOLITAN EDIS0N COMPANY JERSEY CENTPAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-201 THREE MILE ISLAND NUCLEAR STATION. UNIT N0. 1 4
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 187 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear, Corporation, et al.
(the licensee), dated April 11, 1994, 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; 8.
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 tii) that such activities will be conducted in compliance w N 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 and all applicable requirements have been satisfied.
9407210186 940714 PDR ADOCK 05000289 P
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's 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.
DPR-50 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.187, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
b J r F. Stolz, Director -
oject Directorate I-4 dWisionofReactorProjects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 14, 1994
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ATTACHMENT TO LICENSE AMENDMENT N0.187 FACILITY OPERATING l,ICENSE NO. DPR-50 DOCKET N0. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3-95 3-95 4-35 4-35 4-35a (Deleted) 4-36 4-36 4-37 4-37 i
3.19 CONTAINMENT SYSTEMS 3.19.1 CONTAINMENT STRUCTURAL INTEGRITY Applicability:
Applies to the structural integrity of the reactor building.
OBJECTIVE:
To verify containment structural integrity in accordance with the inservice l
tendon surveillance program for the reactor building prestressing system.
Specification 3.19.1.1 With the structural integrity of the containment not conforming to the inservice tendon surveillance program requirements of 4.4.2.1 for the tendon lift off forces, perform an engineering evaluation of the structural integrity of the containment to determine if COLD SHUTDOWN is required.
The margins available in the containment design may be considered during the investigation.
If the acceptability of the containment tendons cannot be established within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.19.1.2 DELETED l
3-95 Amendment No. SP, Jgg, 187
4.4.2 Structu-al Intearity Specification 4.4.2.1 Inservice Tendon Surveillance Reauirements l
The surveillance program for structural integrity and corrosion protection conforms to the recommendations of the U.S. NRC Regulatory Guide 1.35,
" Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete l
Containment Structures." The detailed surveillance program for the prestressing system tendons shall be based on periodic inspection and mechanical tests to be performed on selected tendons.
l 4.4.2.1.1 DELETED i
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4-35 Amendment No. 57, 95, J27,157,187
4.4.2.1.2 DELETED 4.4.2.1.3 DELETED i
4.4.2.1.4 Tendon Surveillance Previous Inspections The tendon surveillance shall include the reexamination of all abnormalities (i.e., concrete scaling, cracking, grease leakage, etc.) discovered in the previous inspection to determine whether conditions have stabilized.
The inspection program shall be modified accordingly if obvious deteriorating conditions are observed.
4.4.2.1.5 Inspection for Crack Growth at Dome Tendons in the Rina Girder Anchorage Areas Concrete around the dome tendon anchorage areas shall be inspected for crack growth during ten and 15 year inspections by monitoring cracks greater than 0.005 inch in width.
Select as a minimum nine dome tendon anchoring areas having concrete cracks with crack widths 0.005 inch.
In the selection of dome tendon anchoring areas' to be monitored, preference shall be given to those areas having cracks greater than 0.005 inch in width. The width, depth (if depths can be measured with simple existing plant instruments, (i.e., feeler gauges, wires) and length of the selected cracks shall be measured and mapped by charting.
This inspection may be discontinued, if the concrete cracks show no sign of growth.
If, however, these inspections indicate crack growth, an investigation of the causes and safety impact should be performed.
i 4-36 Amendment No. 59, Jgp, 187 1
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1 4.4.2.1.6 Reports
- a. Within 3 months after the completion of each tendon surveillance a special report shall be submitted to the NRC Region I Administrator.
This Report will include a section dealing with trends for the rate of prestress loss as compared to the predicted rate for the duration of the plant life (after an adequate number of surveillances have been completed).
- b. Reports submitted in accordance with 10 CFR 50.73 shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and any corrective actions taken.
4.4.3 DELETED BASES i
For ungrouted, post-tensioned tendons, this surveillance requirement ensures l
that the structural integrity of the containment will be maintained in accordance with the provisions of the THI-1 Reactor Building Structural Integrity Tendon Surveillance Program. Testing and frequency are consistent with the recommendations of Regulatory Guide 1.35, as described in the FSAR.
The modified visual inspection requirements pertaining to the dome tendons in the ring girder were implemented as a result of:
- 1) discovery of ring girder voids in 1977 and the potential that more undetected voids in the ring girder could exist, and 2) the number of dome tendon bearing areas having cracks.
appeared to be growing with time (Reference Amendment No. 59).
REFERENCES (1) UFSAR, Section 5.7.5 - Tendon Stress Surveillances 4-37 Amer. ament No. JpS, JES, JEg, 187