ML20217D274
| ML20217D274 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/01/1997 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20217D271 | List: |
| References | |
| NUDOCS 9710030101 | |
| Download: ML20217D274 (8) | |
Text
.
o Procedures, Programs and Manuals 5.6 5.6 Frocedures, Programs and Manuals
)
^
9.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake.a loss of coolant accident,oramainsteamlineor.feedwaterline break, as specified in 5.6.2.10.3.c, above.
10 Tube Inspection means an inspection of the entire OTSG tube as far as possible.
b.
The OTSG shall be determined OPERA 8LE after completing exceeding the plugging /slee(plug or sleeve all tubcs the corresponding actions vin limit and all tubes containing through wall cracks required by Table Specifica(and Table 5.6.2-3 iftion 5.6.2.10.2.d are utilized).
Defective 5.6.2 2 he provisions of tubes may be repaired in accordance.with the B&W process ;or method) equivalent to the method described in report BAW-2120P.
c.
In service tubes with rit-like IGA-indications-in the first span of the "B" OTSG shall be monitored for growth of these indications in the following fashion:
1.
Tubes that were inspected with the high frequency bobbin probe in 1997 shall have the indicated %
throughwall value from the current inspection compared to the 1997 indicated % throughwall value. A high frequency bobbin probe comparable to the high frequency bobbin probe used in the
.1997 inspections shall be used for this Comparison.
2.
Tubes shall have the indicated voltage on the 400 kHz channel from the current inspection compared to the 1997 indicated voltage on the 400 kHz channel. A mid-range frequency bobbin probe comparable to the mid range frequency bobbin probe used in the 1997 inspections shall be used for this comparison.
5.6.2.11 Secondary Water Chemistry Program This program provides controls for mo?itoring secondary water chemistry to inhibit steam generator ube degradation and low pressure turbine disc stress corrosi,n cracking.
The program shall include:
a.
Identification of a sampling schedule for the critical variables and control points f?r these variables; b.
Identification of the procedures used to measure the values of the critical variables; (continued)
Crystal River Unit 3 5.0-17 Amendment No.
I 9710030101 971001 PDR ADOCK 05000302 p.
I Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued)
The following Special Reports shall br submitted:
a.
When a Special Report is required by Condition B or F of LCO 3.3.17, " Post Accident Monitoring (pAH) d within the Instrumentation," a report shall be submitte following 14 days.
The report shall outline the preplanned alternate method of monitoring,d schedule for restoring the the cause of the i
inoperability, and the plans an instruicentation channels of the Function to OPERABLE status.
b.
Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 1
30 days. The report shall include a description of the tendoncondition,theconditionoftheconcrete(es)ecially at tendon anchorages), the inspection procedures, tie tolerances on cracking, and the corrective action taken.
I c.
Following each inservice ins)ection of steam generator (OTSG tubes, the NRC shall se notified of the following prior)to ascension into MODE 4:
1.
Number of tubes plugged and sleeved 2.
Crack like indications in the first span 3.
An assessment of growth in the first span indications, and 4.
Results of in situ pressure testing, if performed.
The complete results of the OTSG tube inservice inspectioa shall be submitted to the NRC within 90 days following the j
completion of the inspection. The report shall include:
1.
Number and extent of tubes inspected, 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, 3.
Location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each first span IGA indication, and 4.
Identification of tubes plugged and tubes sleeved.
(continued)
Crystal River Unit 3 5.0-29 Amendment No.
l
-=-.
Reporting P/quirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued) 5.
For first span "B" OTSG pit-like IGA, a summary of analyses performed to determine if estimated leakage based on the projected end-of-cycle percent throughwall distribution exceeds the leak limit (determined from the licensing bacis dose calculation for the main steamline break) for the next operating cycle.
6.
For first span "B" 0TSG pit-like IGA, a summary of analyses performed to determine if the calculated conditional burst probability based on the projected end-of-cycle (or if not practical, using the actual measured end,of-cycle) percent throughwall distribution exceeds 1x10', and an assessment of the safety significance of the occurrence if exceeded.
Results of OTSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant operation. This report shall provide a. description of investigations conducted to determine c:iuse of the tube degradation and corrective measures taken to prevent recurrence.
Crystal River Unit 3 5.0-29A Amendment No.
I I
U: S Nucl3ar Rsgulttory Commission 3F1097 21 ATTACHMENT B LICENSE AMENDMENT REQUEST No. 221, REVISION 0 "B" ONCE-THROUGH STEAM GENERATOR TUBE SURVElLLANCE PROGRAM Set of Changed Pages With New or Reviesd Information Shown in Shadowed Font
Procedures, Programs and'Hanuals 5.6
' ' 5.6 Procedures, Programs and Manuals 9.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake a loss-of-coolant accident, or a main steam line or feedwater line break, as specified in 5.6.2.10.3.c, above.
10.
Tube Inspection means an inspection:of the entire OTSG tube as far as possible. -
b.
The OTSG shall be determined OPERABLp iter completing the corresponding actions exceeding the plugging /slee(plug or st..ve all tubes vir, limit and all tubes containing through-wall cracks -required by Table Specifica(and Table 5.6.2-3 iftion 5.6.2.10.2.d are utilized).
Defective 5.6.2-2 he provisions of tubes may be repaired in accordance with the B&W process Lor method) equivalent to the method described in repord BAW-2120P.
FQICisFvTEiMi6iiNiiWiiifil'i Ei?DiihdiEifliis?f6Hhi
~ firstispanioff thet"BNOTSG;shal' tbalmonitoredifor growthioRthtseitgdica11oasilnithgl{g]lging;faghfp61 g^ g TsSiitthii ssFirisisistidritthithiiWTiHYrfissisdy bobbin':probeEinkl9971shalliha#ithesindicatidg
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i throughwal i d al ue a fron; the:f current ei nspect iog comparod ito tthe9199Bi nd i cated ttbroulomparabl,e hwall
-value W Aihi h! frequency! bobbin obe:
tostheihighli requencprbobbinip MusedLinthe~
Co* Pat!1sgg pggshaAlbeluised this' 199711nspect
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2ETubiirsWillihiViithillidlEitidW61Lti6iliETthiM00 -
kHuchanneMfronAthescurrentMnspectionicompgred'
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totthe>1997sindicatedsvoltageionsthe)400!kHY ^~
'hanne1 N:Aimiderange Mrequency3bobbiiniprobe _ bi c
compa rabl e i to t theY mid 4 range 2f requencys bobbi n t! Pro usedti ns th631997Mnspec t_t on sispal]1belusedifgf" thisaRattrisom 5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry-to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking.
The program shall include:
a.
Identification of a sampling schedule for the critical variables and control points for these variables; b.
Identification of the procedures used to measure the values of the critical. variables; (continued)
Crystal River Unit 3 5.0-17 Amendment No. M 4 hlid Until "cfuci 11 Only
l, Reporting Requirements 5.7 5.7 Reporting Requirements 4
5.7.2 Special Reports (continued)
The following Special Reports shall be submitted:
a.
When a Special Report is required by Condition B or F of LC0 3.3.17, " Post Accident Monitoring (PAM).
Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status, b.
Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days.
The report shall include a description of the tendon condition, the condition of the concrete (es)ecially at tendon anchorages), the inspection procedures, tie tolerances on cracking, and the corrective action taken, c.
Following each inservice inspection of steam generator (OTSG) tubes, the NRC shall be notified of the following prior to ascension into MODE 4:
1.
Number of tubes plugged and sleeved 2.
Crack-like indications in the first span 3.
An assessment of growth in the first span indications, and 4.
Results of in-situ pressure testing, if performed.
The complete results of the OTSG tube inservice inspection shall be submitted to the NRC within 90 days following the completion of the inspection. The report shall include:
1.
Number and extent of tubes inspected, 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, 3.
Location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each first span IGA indication, and 4.
Identification of tubes plugged and tubes sleeved.
(continued)
Crystal River Unit 3 5.0-29 Amendment No. M4 hlid Until Refuel 11 Only
e' h
Reportina Requir:ments 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued)
' ""7F6EflFICipah?B"IOTSG71t311kTIGGI?siiinmWyTf ST
" analyses performeditotdeterminejifgestimatedsleaksii ba sed (on tthe? projec t ed : end -of-cycl el percent? throdghwil l d i s t ri bu t i 6hi exceed si theil e akt l imi tE (det e rmi ned if roni~~~'
~
the licensing!basisTdose ealcUlationiforf thei'mairf ~
f
)t_e_aml i n;elbre a k)jfont help lextiop,e rat ijgf ckgl ef~~'
6Elfsf!!fi~ritJijfinH BSOTSG7pi t?1 i kfilGARi7sdriiiirry?6f
.analysesjperformed;toi:;de.termineliff the2calcul_ato _id cond i ti onal; burs ti probabil i tyi based Lon1 thel probt end-of; cycl eC(o rf i fi n~oti practicil W u s t'ngT the7 actiial measur'ed endjof; cyclepercentithroughwall?distvibuff6ii exce.edsfix1_0' Jand(ioccurrenceHfiexceeded.;an; a s s es smin signi.ftc_angefofjthe Results of 0TSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant operation. This report shall prcvide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence, l Crystal River Unit 3 5.0-29A Amendment No. M 4 hlid Until Refuel 11 Only l
J U. S. Nucle:r Rigul:t:ry Commissi:n 3F1097-21 +- ATTACHMENT C List of Regulatory Commitments The following table identifies those actions committed to by Florida Power Corporation in this document. Any other actions discussed in the submittal represent intended or planned actions by Florida Power Corporation. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Manager, Nuclear Licensing, of any questions regarding this document or any associated reputatory commitments. ID Number Commitment Commitment Date 3F1097-21-1 FPC will utilize the data acquisition and Programmatic analysis variables as provided in Page 8, Commitment upon Attachment A. approval of LAR No. 221, Revision 0. 3F1097-21-2 FPC will complete the operational Programmatic assessments for rirst span pit-like IGA within Commitment upon 90 days following plant restart. However, a approval of LAR No. preliminary assessment will be performed 221, Revision O. prior to actual tube plugging nr repair activities to ensure that repair criteria being implemented are sufficient to support the duration of the planned operating cycle. 3F1097-21-3 FPC will complete condition monitoring Programmatic assessments for first span pit-like IGA within Commitment upon 90 days following plant restart, approval of LAR No. 221. Revision 0. 3F1097-21-4 in the event that a structural integrity Programmatic condition is identified that exceeds the Commitment upon leakage limits or calculated conditional burst approval of LAR No. probability described above, the condition 221, Revision 0. monitoring results will be reported to the NRC in accordance with the guidance found in 10 CFR 50.72.}}