ML16161A270
| ML16161A270 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/19/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML16161A271 | List: |
| References | |
| NUDOCS 9710010212 | |
| Download: ML16161A270 (4) | |
Text
CORRECTION TO LICENSE AMENDMENT NO. 225 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 225 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 222 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Insert 4.4-16 4.4-16 4.4-16a 4.4-16a 4.4-16b 4.4-16b 9710010212 970919 PDR ADOCK 05000269 P
- 5. If the measured prestressing forces from consecutive surveillances for the same tendon, or tendons in a group, indicate a trend of prestress lovs larger than expected and the resulting prestressing forces are likely to be less than the minimum required for the group before the next scheduled surveillance, additional lift-off testing shall be done so as to determine the cause and extent of such occurrence.
The condition shall be considered as an indication of abnormal degradation of the reactor building.
In the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
- b. Perform tendon detensioning, inspections, and material tests on a tendon from each group.
A randomly selected tendon from each group shall be completely detensioned in order to identify any broken or damaged wires and to determine the following conditions over the entire length of a removed tendon wire sample (this wire sample should be the broken wire if so identified)o
- 1. Tendon wires are free of corrosion, cracks, and damage, and
- 2. Minimum tensile strength of 240,000 psi (guaranteed ultimate tensile strength of the wire material) exists for at least three wire samples (one from each end and one at mid-length) cut from the removed wire.
Failure to meet requirements of 4.4.2.2.b shall be considered as an indication of abnormal degradation of the reactor building. In the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
- c. Retension tendons detensioned for inspection to a force at least equal the force recorded prior to detensioning or the predicted value at the time of inspection, whichever is greater, but do not exceed 70% of the guaranteed ultimate tensile strength of the tendon wire material.
Tendon seating force tolerance shall be -0 / +6W.
During retensioning of these tendons, change in load versus elongation should be measured at varying levels of force.
The following table provides levels of force, pressure, and elongation at which measurements should be taken, Porce (Kips)
Pressure (psi) Elongation (In)
PTP DCONEE UNITS 1, 2, & 3 4.4 -I Amendment No. 225 (Unit 1)
Amendment No. 225 (Unit 2)
Amendment No. 222 (Unit 3)
Step 1 Step 2 LOF OSF Where:
Total Elongation (actual) * (LOF-PTF) Elongation PTF - Pretensioning Force necessary to bring the tendon into a slightly stressed condition to remove slack and seat the buttonheads.
Step 1 An intermediate force approximately equally spaced between PTP and LOP.
LOP - Lock Off Force at which the tendon is seated on the shims.
OSF - Overstress Force at which the maximum elongation is measured.
If the elongation corresponding to a specific load differs by more than 10% from that recorded during the original installation, an investigation should be made to ensure that the difference is not related to wire failures or slip of wires at anchorages. This condition shall be considered as an indication of abnormal degradation of the reactor building. In the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
- d. Verify acceptability of the sheathing filler grease by assuring that:
- 1. No free water is present and no changes in the presence or physical appearance of the sheathing tiller grease occur.
- 2. Amount of grease replaced does not exceed 5V of the net duct volume when injected at +/-lo of the specified installation pressure.
- 3. Minimum grease coverage exists for the different parts of the anchorage system.
- 4. Reactor building exterior surface does not exhibit grease leakage that could affect reactor building integrity.
- 5. Chemical properties of the sheathing filler grease are within the following tolerance limits:
Water Content 0 - 10 (by dry wt.)
Chlorides 0 - 10 ppm Nitrates 0 - 10 ppm Sulfides 0 -
10 ppm UNITS 1, 2. & 3
- .* 1 Amendment No.225 (unit 1)
Amendment No. 225 (Unit 2)
Amendment No. 222 (Unit 3)
Reserve Alkalinity
> 5OW of installed (Base Numbers) value;
> 0 (for older grease)
Failure to meet requirements of 4.4.2.2.d shall be considered as an indication of potential abnormal degradation of the reactor building. in the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
4.4.2.3 End Anchorages and AdIacent Concrete Surfaena As an assurance of the structural integrity of the reactor building(s), tendon anchorage assembly hardware (such as bearing plates, stressing washers, wedges, and buttonheads) of all tendons selected for inspection shall be visually examined. Tendon anchorages selected for inspection shall be visually examined to the extent practical without dismantling the load bearing components of the anchorages. Top and bottom grease caps of all vertical tendons shall be visually inspected to detect grease leakage or grease cap deformations. The surrounding concrete should also be checked visually for indication of any abnormal condition.
Significant grease leakage, grease cap deformation or abnormal concrete condition shall be considered as an indication of abnormal degradation of the reactor building.
In the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
4.4.2.4 Reactor Buildina Surfaces The exterior surface of the reactor building(s) ahould be visually examined to detect areas of large spall, severe scaling, D-cracking in an area of 25 sq. ft. or more, other surface deterioration or disintegration, or grease leakage.
Each of these conditions can be considered as evidence of abnormal degradation of structural integrity of the reactor building(s).
This inspection may be performed prior to the Type A containment leakage rate test (Refer to Technical Specification 4.4.1).
In the event of an indication of abnormal degradation, refer to Technical Specification 3.6.7.2.
CONE
- UNITS 1, 2, a 3 4.4.-(4 Amendment No. 225 (Unit 1)
Amendment No. 225 (Unit 2)
Amendment No. 2 22 (Unit 3)