ML20196K627
| ML20196K627 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/28/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20196K630 | List: |
| References | |
| NUDOCS 9907090229 | |
| Download: ML20196K627 (9) | |
Text
1 i
n Rec n
oq'o' UNITED STATES.
/'
' t, NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 205S5 A.,.....J;$
- FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION.
I CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE. INC.
CITY OF TALLAHASSEE
- DOCKET NO. 50-3_02 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICEtRE Amendment No.180 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the licensees), dated August 31,1998, as revised on March 18,1999, complies with the standards and requirements of the Atomic Energy Act of 1J' S4, as amended j
(the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of ihe 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 (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and secunty or to the health and safety of the public; and 9907090229 990628 PDR ADOCK 05000302 p
PDR 3
. 4 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licenau amendment, and paragraph 2.C(2) cf Facility Operating License No. DPR-72 is hereby amended to read as fcilows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, are hereby incorporated.in the license. Florida Power Corporation shall operate the facility in accordance with the Technical o
Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented prior to commencing cycle 12 operation.
FOR THE NUCLEAR REGULATORY COMMISSION Y $.
W
~
Sheri R. Peterson, Chief, Section 2 Project Directorate ll Division of Project Licensing Management Office of Nuclear Reactor Regulation Date of issuance: June 28,1999 L_.
ATTACHMENT TO LICENSE AMENDMENT NO.180 TO FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contains vertical lines indicating the area of change.
Remove Pace Insert Pace 5.0-16 5.0-16 5.0-17 5.0-17 50.17A 5.0 5.0-25 5.0-26 5.0-26 5.0-29 5.0-29
Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) 4.
. Acceptance criteria:
a.
Vocabulary as used in this Specification:
1.
Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pre;sure boundary.
2.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3.
Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube.
4.
Degraded Tube means a tube containing degradation 2 20% through-wall but < 40% through-wall in the pressure boundary.
5.
% Degradation /% Through-wall means the percentage of the tube (pressure boundary) wall thickness affected or removed by degradation.
6.
Defective Tube means a tube containing degradation 2 40% through-wall in the pressure boundary.
Any tube which does not permit the passage of the eddy-current inspection' probe shall be deemed a defective tube.
7.
Pit-like Intergranular Attack (IGA) indication means a bobbin coil indication confirmed by Motorized Rotating Pancake Coil (MRPC) or other qualified inspection techniques to have a i
volumetric, pit-like morphology characteristic of ICA.
)
(continued)
Crystal River Unit 3 5.0-16 Amendment No.180
)
1
]
F Procedures, Programs anJ Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) 8.
Plugging / Repair Limit means the extent of pressure boundary degradation beyond which the tube shall either be removed from service by installation of plugs or the area of degradation shall be removed from service (a new pressure boundary established) using an Approved Repair Technique.
The plugging / repair limit is 40% through-wall for all pressure boundary degradation.
9.
Unservicesble describes the condition of a tube if it leaks or contains a defect large enough to o
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 OTSG tube pressure boundary.
J
- 11. Approved Repair lechnique means a technique, other than plugging, that has been accepted by the NRC as a methodology to remove or repair degraded or I
defective portions of the pressure boundary and to establish a new pressure boundary.
Following are Approved Repair Techniques:
a)
Sleeve installation in accordance with the B&W process (or method) described in report BAW-2120P.
No more than five thousand sleeves may be installed in each OTSG.
b)
Installation of repair rolls in the upper tubesheet in accordance with the Framatome Technologies Incorporated processes (or methods) described in reports BAW-2303P and BAW-2342P.
The repair process (either single roll or double roll) may be performed once per tube.
The repair roll area will be examined using eddy-current methods following installation.
The repair roll must be free of imperfections and degradation for the repair to be considered acceptable.
(continued)
Crystal River Unit 3 5.0-17 Amendment No.180 t
Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) l The repair roll in each tube will be inspected during each subsequent inservice inspection while the tube with a repair roll is in service.. The repair roll will be considered a specific limited area and will be excluded from the random samaling.
No credit will be taken for meeting t1e minimum sample size.
If primary-to-secondary leakage results in a shutdown of the plant and the cause is determined to be degradation in a repair roll, 100% of the repair rolls in that OTSG shall be o
examined.
If that inspection results in entering Category C-2 or C-3 for specific limited area inspection, as detailed in Table 5.6.2-3, 100% of the repair rolls shall be examined in the other OTSG.
i b.
The OTSG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging / repair limit) required by Table i
5.6.2-2 (and Table 5.6.2-3 if the provisions of Specification 5.6.2.10.2.d are utilized).
I There are a number of OTSG tubes that have the potential to exceed the tube plugging / repair limit as a l
result of tube end anomalies.
Defective tubes will be repaired or plugged during the next outage of sufficient duration.
An evaluation has been performed which confirms that optrability of the CR-3 OTSGs will not be impacted with those tubesin service.
l l
c.
Inservice tubes with pit-like IGA indications in the "B" OTSG first span shall be monitored for growth of these indications by using a test probe equivalent to the hiah frequency bobbin probe used in the 1997 inspection.
T$e indicated percentage throughwall value from the current inspection shall be compared to th' indicated percentage throughwall value from the 1997 in_pection.
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 5.0-17A Amendment No.180
Procedures, Programs and Manuals 5.6 TABLE 5.6.2-2 (page 1 of D OTSG TUBE INSPECTION 1st Sample Inspection 2nd Sample Inspection 3rd Sample Inspection Action Action Action Sample Size Result Required Result Required Result Required A minimum of 5 C-1 None N/A N/A N/A N/A tubes per OTSC e
C-2 Plug or C-1 None N/A N/A repair l
defective tubes and C-2 Plug or C-1 None inspect an repair l
additional defective 25 tubes in tubes and this OT5G.
inspect additional 45 tubes in this OTSG.
C-?
Plug or repair l
defective tubes.
C-3 Perform action for C-3 result of first sample.
C-3 Perform N/A N/A action for C-3 result of first sample.
C-3 Inspect all All other None N/A N/A tubes in OT5Gs are this OTSG, C-1 ~
plug or repair I
defective
- tubes, 5(ee OT5Gs Perform N/A N/A inspect 25 C-2 but no action for tubes in additional C-2 result each other OTSGs are of second OT5G, and C-3 sample.
notify NRC per
- dditional Inspect all N/A N 'A 10CFR50.72 OT5G is C-3 tubes in each OTSC, plug or repair I
defective j
tubes, and notify NRC per 10CFP50.72.
S = 3 N/n E Where N is the number of OTSGs in the unit and n is the number of GTSGs inspected during inspection period.
Crystal River Unit 3 5.0-25 Amendment No.180
Procedures, Programs and Manuals 5.6 TABLE'5.6.2-3 (page 1 of 1)
SPECIFIC LIMITED AREA INSPECTION 1st Sample Inspection of a 2nd Sample Inspection of a
" Specific Limited Area"
" Specific Limited Area" Sample Size Result R ui ed Result R
ed 100% of area C-1 Nor.e N/A N/A in both OTSCs C-2 Plug or repair N/A N/A l
defective tubes.
C-3 Plug or repair N/A N/A l
defective
- tubes, 100% of area C-1 None N/A N/A in one OTSG C-2 Plug or repair C-1 None l
j defective tubes and Plug or inspect 100%
C-2 repair l
j of defective corresponding
- tubes, area in other Plug or OT5G C-3 repair I
defective tubes.
C-3 Plug or repair C-1 None l
defective Plug or tubes.nd C-2 repair l
l inspect 100%
defective of tubes.
corresponding area in other Plug or OT5G.
C-3 repair i
defective tubes.
CrystalitiverUnit3 5.0-26 Amendment No.180
Reporting Requirements 5.7 5.8 Reporting Requirements
,5.7.2 Special Reports (continued)
-The following Special Reports shall be submitted:
When a Special Report is required by Condition B or F of a.
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 an,d 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
.e 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 (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.
Following each inservice inspection of steam generator
.c.
(OTSG). tubes, the NRC shall be notified of the following prior to ascension into MODE 4:
.1.
Number of tubes plugged and repaired, l
'2.
Crack-like indications and assessment of growth for indications in the first span, 3.
Results of in-situ pressure testing, if periormed.
'Results of OTSG tu'e inspections that fall'into Category C-3 d.
b shall be reported to the NRC in accordance with 10CFR50.72.
The complete results of the OTSG tube inservice inspection I
e.
shall be submitted to the NRC within 90 days after breaker closure following restart.
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 i
span IGA indication, and'
{
4.
Identification of tubes plugged or repaired and specification of the repair methodology. implemented for each tube.
Crystal River.. Unit'3 5.0 Amendment No.180 L