ML102910557
| ML102910557 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/12/2009 |
| From: | Herrin D W Progress Energy Florida |
| To: | Masters A D NRC/RGN-II/DCP/CPB1 |
| References | |
| FOIA/PA-2010-0116 | |
| Download: ML102910557 (7) | |
Text
_745 *Masters, Anthony From: Sent: To: Cc:
Subject:
Attachments:
Herrin, Dennis W. [Dennis.Herrin
@ pgnmail.com]
Thursday, November 12, 2009 8:28 AM Masters, Anthony Portmann, Rick FW: NRC SIT Question Responses!NRC Request #50 Information-Portmann.docx;
!NRC Request #58 Information-Portmann.docx; Optical Comparitor Calibration Certs.pdf;
!NRC Request #49 Information.docx Lead Engineer -Licensing.&
Regulatory Programs Progress Energy Florida, Inc.Crystal River Unit 3 352-563-4633 Voicenet 240-3299 D~ennis.Herrin@pqnmail.com From: Portmann, Rick Sent: Thursday, November 12, 2009 8:11 AM To: Herrin, Dennis W.Cc: Dye, Linda F
Subject:
NRC SIT Question Responses Dennis -Attached are 3 more responses to Anthony Masters questions.
I've updated the NRC folders and will be taking a copy to the NRC Trailer. If you could also forward this to him if he is off-site.
Thanks, Rick 1.~72,2-7 Request #50, NRC SIT Question Information
- 50. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Section 3.7.2.11 states as an prerequisite to "verify that stressing jacks, pressure gauges, comparators, and all other measuring devices have been calibrated per Step 3.5.3.1..." Are the measuring devices used calibrated per Step 3.5.3.1?Response to the above question: Measuring devices are calibrated per Step 3.5.3.1 of SP-182. An example of the certification records for one of the past surveillances can be found on pages 58-82 in the 6 th surveillance report {WR 341602 6th-Surv.pdf}.
This report can be found: L:\Shared\2009 NRC SPECIAL INSPECTION TEAM Q-A\WILLIAMS Q-A\Request 24, Q18 Response Info-Portmann\IWL
-Tendon Surveillance History Request #58, NRC SIT Question Information
- 58. FSAR, Section 5.2, Section 5.2.5.2.1.1.h.5 states: The surveillance was performed 1, 3, and 5 years after the initial containment structural integrity test and is performed every 5 years thereafter.
A report of each inspection will be recorded and significant deterioration or abnormal behavior reported to the Commission.
Are significant deterioration or abnormal behaviors being reported to the Commision?
Response to the above question: Yes -Significant deterioration or abnormal behaviors are being reported to the Commission.
SP-182 (Para's 5.3.2 and 5.3.4) and the Improved Technical Specifications (5.7.2 Special Reports) describe the reporting requirements.
SP-182: REACTOR BUILDING STRUCTURAL INTEGRITY TENDON SURVEILLANCE PROGRAM 5.3.2 Reportable Conditions In the event that the acceptance criteria in Section 3.6, Acceptance Criteria is not met, the Surveillance Contractor shall notify Engineering within 1 working day. Engineering shall follow the reporting process defined in CP-151: External Reporting Requirements (Step 2.1.3.5).
If Engineering determines that there is abnormal degradation of the containment structure (based on the contingency actions in Section 5.2: Contingencies);
CR3 shall submit a report to the NRC within 30 days of the current surveillance.completion.
This report shall include a description of the degradation, operability determination, root cause determination and the corrective action.5.3.4 Evaluation Summary Report A written summary report of the results and conclusions for each inspection period must be prepared within 90 days of the completion of the tests and inspections.
The report shall also include items that did not meet the acceptance criteria and were evaluated by Engineering and address the following:
- the cause of the condition which did not meet the acceptance criteria* the acceptability of the concrete containment without repair of the item* whether or not repair or replacement is required and, if required, the extent, method, and completion date for the repair or replacement
- extent, nature, and frequency of additional examinations This report shall be maintained on file.IMPROVED TECHNICAL SPECIFICATIONS 5.7.2 Special Reports Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report. The following Special Reports shall be submitted:
- b. Any abnormal degradation of the containment structure found during the inspection performed in accordance with ITS 5.6.2.8 shall be reported to the NRC within 30 days of the current surveillance completion.
The abnormal degradation shall be defined as findings such as delamination of the dome concrete, widespread corrosion of the liner plate, corrosion of prestressing elements (wires, strands, bars) or anchorage components extending to more than two tendons and group tendons force trends not meeting the requirements of 10CFR50.55a(b)(2)(ix)(B).
The report shall include the description of degradation, operability determination, root cause determination and the corrective actions.
G '7E:---1:7 Q 0 DEC-10-97 WED 15:30 PREC[S[UK
ýUlvVtILLHNUt rflA 11U. 'C'j I Cal ibrat ion MIEWEST GAGE LAB Cer t I i iCat e 299 B(ND ST.ELK QWOVE VILLAGE, IL. 60007 (708)439-9220 INSPECTION REPORT DATE: 06/08/95 S.O. NO. 1229308 CUSTOOER:
Precision Surveillance P.O. NO. 649 DESCRIPTION:
1.6" Glass Reticle Scale, GRCS-l REQUIRED (INTERVAL)
ACTUAL (LENGTH).000.000.000.000.000.000.000.000.000.000 TO T0 TO TO TO TO 1IX)TO TO TO.002.004.006.008.010.01Z.014.016.018.020.0020.0040.0060.0080.0100.0120.0140.0160.0180.0200* Accuracy +/-.00005 INSPECTOR:
Jeffrey Yallmann SIGNEDI. ) -/NIST TRACEABILITY NO. 821/252017-93 NIST DATE; 08/12/94 Measurements made ih accordance with MIL-STD 4566ZA.The size standards used in measuring were calibrated traceable to the National Institute of Stando4 Technology, Washington, D.C.
-Ur' 1' 1?ý f 0 1:p o DEC-10-97 WED 15:31 PRECISIUNýFA IAU-ro uu i Request #49, NRC SIT Question Information
- 49. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Section 3.7.1 recommends equipment for implementation of this inspection and 3.7.1.12 lists "optical comparators with 0.005 inch accuracy for measuring crack widths in concrete" Is this being used? VT-07-111 and VT-07-289 do not have it listed in the inspection equipment area on the reports. These reports list a 6" scale and measuring tape. Is 0.005 inch accuracy (or the 0.010 inch acceptance criteria section 3.6.2 states) possible with these?Response to the above question: The inspection reports referenced were performed as part of the IWL Examinations.
The controlling procedures are NDEP-0620 and NAP-02. The SP-182 surveillance procedure referenced is used in conjunction with the Tendon examinations (not the IWL Examinations).
The accuracy stated comes from the PSC Procedures and equipment utilized for the Tendon Examinations.
An example of the certification record for one of the past surveillances can be found on pages 77-78 of the 6 th surveillance report {WR 341602 6th-Surv.pdf}.
Copies of the certifications have been enclosed in this file. This report can be found: L:\Shared\2009 NRC SPECIAL INSPECTION TEAM Q-A\WILLIAMS Q-A\Request 24, Q18 Response Info-Portmann\IWL
-Tendon Surveillance History