ML090270928
| ML090270928 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/26/2009 |
| From: | Lahti L Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML090270928 (9) | |
Text
Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 January 26,2009 Technical Specification 5.6.7 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Containment Structural 1ntearit-v Surveillance Proaram 35-Year Tendon Surveillance
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. has recently completed the subject surveillance for the Palisades Nuclear Plant (PNP). The inservice inspection summary report for the 35-year tendon surveillance is enclosed. The summary report is prepared in accordance with ASME Section XI, 1998 Edition, 1998 Addenda, and 10 CFR 50.55a(b)(2)(viii). The summary report is being submitted in accordance with PNP Technical Specification 5.6.7, which requires submittal of a report within 90 days after completion of the tests. Surveillance testing activities were completed on November 3,2008.
Summaw of Commitments This letter closes an existing commitment. There are no new commitments The following commitment in the 30-year tendon surveillance report, submitted to the NRC on April 7, 2003, has been completed:
Inspect containment dome tendon D 1-38 and adjacent tendons D 1-36 and D 1-40 for free water and chemically combined water during the 35-year tendon sun/eillance.
Laurie A Lahti Licensing Manager Palisades Nuclear Plant
Document Control Desk Page 2 Enclosure CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC
ENCLOSURE 1 PALISADES NUCLEAR PLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT 2008 CONTAINMENT STRUCTURAL INTEGRITY SURVEILLANCE PROGRAM, INSERVICE INSPECTION
SUMMARY
Submitted in accordance with American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice lnspection of Nuclear Plant Components," Article IWA-6000, "Reports and Records," 1998 Edition, 1998 Addenda
- 1.
Date:
August 2008 through November 2008
- 2.
Company Headquarters:
Entergy Nuclear Operations, lnc.
1340 Echelon Parkway Jackson, Mississippi 3921 3
- 3.
Plant:
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043
- 4.
Unit No:
One
- 5.
Commercial Service Date:
December 31, 1971
- 6.
Major Component Inspected:
Component Manufacturer Equipment Number Post-tensioning System Bechtel N-54A
- 7.
Completion Date of Examination:
November 3, 2008
- 8.
Code Inspector:
P.M. McCarthy
- 9.
Authorized Inspection Agency:
Hartford Steam Boiler of Connecticut Hartford, Connecticut Page 1 of 7
PALISADESNUCLEARPLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT 1.0 PURPOSE Entergy Nuclear Operations, Inc (ENO) has completed inspection activities and is providing this summary report of examinations, inspections and corrective actions related to the 35-year containment tendon surveillance. The surveillance program is required by Palisades Nuclear Plant (PNP) Technical Specification (TS) 5.5.5, "Containment Structural Integrity Surveillance Program." All activities were performed in accordance with ASME Section XI, Subsection IWL, "Requirements for Class CC Concrete Components of Light-Water Cooled Plants," 1998 Edition, 1998 Addenda, as modified by 10 CFR 50.55a(b)(2)(viii).
This report is submitted in accordance with TS 5.6.7, "Containment Structural Integrity Surveillance Report," within 90 days after completion of the inspection.
The 35-year tendon surveillance inspection activities were completed November 3,2008.
The inspection activities in the 35-year containment tendon surveillance also included the following inspection activities that were committed to in the 30-year tendon surveillance report submitted to the NRC on April 7, 2003:
Inspect containment dome tendon D 1-38 and adjacent tendons D 1-36 and D 1-40 for free water and chemically combined water during the 35-year tendon sun/eillance.
2.0 EXAMINATION AND INSPECTION SCOPE The examination and inspection scope for the 35-year tendon surveillance is summarized in the following table:
Page 2 of 7
PALISADESNUCLEARPLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT Page 3 of 7 2.1 EXAMINATION Examination Category L-B L-B L-B L-B L-B L-B L-B Item Number L2.10 L2.10 L2.10 L2.20 L2.30 L2.40 L2.50 CATEGORY L-B, Parts Examined Dome Tendons D2-03 (Common)
D l -46 D2-06 D3-37 Vertical Tendons V-334 (Common)
V-90 v-212 V-282 Horizontal Tendons H-42DF (Common)
H-70AE H-44BD H-69BF H-25DF Tendons 01-46 V-282 H-70AE Tendons Tendons Tendons UNBONDED POST-TENSIONING Examination Tendon Tendon Tendon Wire or Strand Anchorage Hardware and Surrounding Concrete Corrosion Protection Medium Free Water Examination Requirement IWL-2522 I WL-2522 IWL-2522 I W L-2523 Detailed
('n--1)
I W L-2525 IWL-2525 SYSTEM Acceptance Standard IWL-3220 IW L-3220 I WL-3220 IWL-3220 I W L-3220 IW L-3220 IWL-3220 Comments Satisfactory Satisfactory Satisfactory Satisfactory Satisfactory Satisfactory Condition Report CR-PLP-2008-04477 Satisfactory Condition Report CR-PLP-2008-03641
PALISADES NUCLEAR PLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT 3.0 ADDITIONAL CORRECTIVE ACTIONS In addition to the regularly scheduled surveillance, the following tests and examinations were conducted to address previous commitments and corrective action requirements associated with the post-tensioning system.
Page 4 of 7 Comments Corrosion Protection Medium Exams were satisfactory for D l -36 and D l -40. Dl-38 moisture exceeded acceptance criteria (CR-PLP-2008-04477)
The exam of D l -40 was satisfactory. Free Water identified
-36 and D l -38 (CR-PLP-2008-03641)
Gaskets were replaced.
4 Controlling Document Commitment 01 5493 (CACTIS 201 11 39)
Commitment 01 5493 (CACTIS 201 1 139)
Work Order 51637926 Deficiency Free water identified in D l -38 during 30 year surveillance.
Free water identified in
-38 during 30 year surveillance.
Grease leakage Examination Category L-B L-B L-A Item Number L2.40 L2.50 L1.10 Parts Examined Dome Tendons and D l -40 and D l -40 Grease Cans
PALISADES NUCLEAR PLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT 4.0 EXAMINATION AND INSPECTION RESULTS AND CORRECTIVE ACTIONS 4.1 The following items did not meet the acceptance criteria of ASME Section XI IWL-3221.3(e), which states, "There is no evidence of free water."
As documented in condition report CR-PLP-2008-03641, during the inspection of tendon D l -38 (southeast end) and D l -36 (southeast end), free water was discovered. D l -38 contained 23 ounces of free water and D l -36 contained one ounce of free water. The sample of water from D l -38 was determined to have a pH of 12.8, which is less prone to cause corrosion of tendon components.
Sample analysis of the water from D l -36 could not be analyzed because of the small quantity. No free water was identified in the opposite end of these tendons. Grease sample analysis results were acceptable for these tendons with the exception of 01-38 water content (see item 4.2 below). Visual examinations were completed on all anchorage hardware with acceptable results. These tendons were also refilled with grease and had acceptable grease replacement versus grease loss ratios. Water infiltration has been documented during previous tendon surveillances at PNP. The cause of water infiltration has been attributed to degraded grease can gaskets, migration through concrete cold joints, and tendon sheathing. Grease forms a protective coating for tendons and associated components and this function has not been compromised by the presence of water.
As required by 10 CFR 50.55a(b)(2)(viii)(E), EN0 has considered the possibility that this condition may exist in inaccessible areas. Based on the results of inspections and tests, it is concluded that the water in tendon Dl-38 due to its location and the existence of a horizontal cold joint near this tendon end anchorage. The water in D l -36 could be caused by migration through the concrete, through the end cap gasket, or from condensation. The cold joint and tendon grease sheathing are not water tight, and can allow water infiltration when sufficient void space exists. Even if this condition exists in inaccessible areas, it is expected that, tendons would meet performance requirements in a similar manner to that documented for accessible areas.
4.2 The following items did not meet the acceptance criteria of ASME Section XI IWL-3221.4, which states, "Corrosion protection medium is acceptable when the reserve alkalinity, water content, and soluble ion concentrations of all samples are with the limits specified in Table IWL-2525-1." The acceptance criteria for water content provided in Table IWL-2525-1 is 10 percent maximum.
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PALISADES NUCLEAR PLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT As documented in condition report CR-PLP-2008-04477, during the analysis of the grease for tendon Dl-38 (southeast end) and V-212 (top end), the water content was determined to be greater than 10 percent. The grease from D l -38 had a water content of 28 percent and V-212 had a water content of 14 percent.
The analysis of the grease from the opposite ends of these tendons determined that the water content was acceptable. All other grease analysis results for these tendons were acceptable. No free water was identified in these tendons with the exception of the southeast end D l -38 (see item 4.1 above). Visual examinations were completed on all anchorage hardware with acceptable results. Tendon liftoff testing was performed on V-212 (35-year surveillance) and D l -38 (30-year surveillance) with acceptable results. These tendons were also refilled with grease and had acceptable grease replacement versus grease loss ratios.
Water infiltration has been documented during previous tendon surveillances at PNP. The cause of water infiltration has been attributed to degraded grease can gaskets, migration through concrete cold joints, and tendon sheathing. Grease forms a protective coating for tendons and associated components and this function has not been compromised by the presence of the water identified.
As required by 10 CFR 50.55a(b)(2)(viii)(E), EN0 has considered the possibility that this condition may exist in inaccessible areas. Based on the results of inspections and tests, it is concluded that the water in tendon Dl-38 due to its location and the existence of a horizontal cold joint near this tendon end anchorage. The water in D l -36 could be caused by migration through the concrete, through the end cap gasket, or from condensation. The cold joint and tendon grease sheathing are not water tight, and can allow water infiltration when sufficient void space exists. Even if this condition exists in inaccessible areas, it is expected that, tendons would meet performance requirements in a similar manner to that documented for accessible areas.
In order to further monitor tendons 01-38 and V-212, work requests have been initiated to track the tendon inspection and refilling of the tendon sheaths with new grease during the 40-year tendon surveillance.
4.3 The following items did not meet the acceptance criteria of ASME Section XI IWL-3211, which states, "The condition of the concrete surface and tendon end anchorage areas is acceptable if the responsible engineer determines that there is no evidence of damage or degradation, corrosion protection medium leakage, or end-cap deformation sufficient to warrant further evaluation or performance of repair/replacement activities."
Page 6 of 7
PALISADES NUCLEAR PLANT ASME SECTION XI, IWL 35-YEAR TENDON SURVEILLANCE
SUMMARY
REPORT Tendon end cap leakage was previously identified and end cap elastomeric component replacement was performed during the 35-year tendon surveillance with work order 51 637926. End cap elastomeric gaskets (main) were replaced on D3-51, D3-12, V-96, V-148, V-154, V-162, V-178, V-26 and V-66. The end cap elastomeric all-thread washers were replaced on vertical tendons V-100, V-134, V-166, V-170, V-174, V-188, V-218, V-14, V-60, V-64, V-70, V-74 and V-80. All vertical tendon elastomeric component material replacements were located at the top end of the tendons on the containment dome. The dome tendon elastomeric component replacements were located on the southeast and south ends respectively. Previous evaluation of these types of leaks has been attributed to grease filling techniques and subsequent heating of the grease by the sun and containment internal heat. Degradation of elastomeric components may also be caused by exposure to the sun. The tendons with end cap gasket replacements were inspected at the affected end for grease coating and free water with acceptable results. The tendons were refilled with grease and had acceptable grease replacement versus grease loss ratios. The leakage was not significant and had no impact on the operability of the containment or the containment post tensioning system. Grease forms a protective coating for tendons and associated components and this function was not compromised by the small amount of leakage noted.
As required by 10 CFR 50.55a(b)(2)(viii)(E), EN0 has considered the possibility that this condition may exist in inaccessible areas. Based on the results of inspections, it is concluded that the level of leakage in inaccessible areas could be the same as accessible areas. However, even if this condition exists in inaccessible areas, it is expected that, tendons would meet performance requirements in a similar manner to that documented for accessible areas.
5.0
SUMMARY
The TS 5.5.5, "Containment Structural Integrity Surveillance Program,
demonstrates continued containment operability by providing assurance that the containment is capable of fulfilling designed operating and accident functions.
Based on an evaluation of the 35-year tendon surveillance results, and after reviewing the acceptable disposition of non-conforming items, EN0 concludes that the containment structure has not experienced abnormal degradation related to the post-tensioning system and continues to be operable.
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