ML20247M907
| ML20247M907 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/23/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247M904 | List: |
| References | |
| NUDOCS 8906050190 | |
| Download: ML20247M907 (19) | |
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- UNITED STATES
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g NUCLEAR REGULATORY COMMISSION '
L eE WASHINGTON, D. C. 20656 3
SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR-54 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A..
The application for amendment by Sacramento Municipal Utility District (the licensee) dated March 19, 1985, as supplemented June 17 and November 25, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 security or to the health and safety of the public; and 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.
B906050190 890523 PDR ADOCK 05000312 P
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s 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment to the Technical Specification shall become effective within 30 days of the issuance date.
The implementation delay is provided to allow time for modification of affected procedures and promulgation of the changes to personnel.
FOR THE NUCLEAR REGULATORY COMMISSION ll
&(( 4tl
- George Knighton, Di ector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulatica
Attachment:
Changes to the Technical Specifications Date of Issuance: May 23, 1989
di: '
l.
ATTACHMENT TO LICENSE AMENDMENT NO.106-FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following~pages of the Appendix "A" Technical Specifications with-the att contain, ached pages..The revised pages are-identified by. Amendment number and vertical lines indicating the area of change.
Remove
-Insert vi vi.
X X
4-51 thru 4-55a 4-51 thru 4-55b 4-57 4-57 4-57a 4-57a 4-57d thru h
dy '
RANCHO SECO UNIT 1~
- TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Section P.Aat
'4.11 prACTOR BUILDING PURGE EXNAUST FILTERING SYSTEM 4-42 4.12 AUXILIARY AND SPENT FUEL BUILDING FILTER SYSTEMS 4-43 4.13 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH 4-44 INERGY LINES OUTSIDE OF CONTAINMENT 4.14 SNUBBERS 4-47 4.15 RADI0 ACTIVE MATERIALS SOURCES 4-48 4.16 Reserved 4-49 4.17 STEAM GENERAIQR1 4-51 4.17.1 Steam Generator sam ~ofe Selection and Inseettien 4-51 4.17.2 Steam Generator Tube Samele Selection and Inseettien 4-51 4.17.3 Inseettien Frequencies 4-53 4.17.4-Definitions 4-54 4.17.5 Resorts 4-54 4.17.6 OTSG Auxiliary Feedwater Header Surveillance 4-55 l
4.17.7 Inspection Acceptance Criteria and Corrective Actions 4-55 4.17,8 Reports 4-55 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE 4-58 4.19 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATIO 4-63 4.20 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIO 4-65 4.21 L1001D EFFLUENTS 4-69 4.21.2 Das.gt 4-72 4.21.2 Dese Calculations 4-72 4.21.3 Lieutd Holduo Tanks 4-73 4.21.4 Liouid Effluent Radvaste Treatment 4-73a Am:ndment No. 75.JJ,(f.#7.$d.106 VI
d' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES (Continued) yglg
?nt 4.6-1 DIESEL GDiERATOR TEST SCHEDULE 4-34j 4.6-2 ADDITIOML RELIABILITY ACTI0f6 4-34k 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUEBERS FUNCTIONALLY 4 47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-S7 4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c 4.17-4 SPECIAL PERIPHERAL GROUP TUBES 4-57d-g 4.17 5 SPECIAL LANE REGION GROUP TUBES 4-57h 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS 4.21-1 RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-70 4.21-2 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84 l
4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE 4-8B REQUIREMENTS 4.34-1 METEOROLOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 MINIMUM SHIFT CREW COMPOSITION 6-2 Amendment No. 28, 66, 76, BB, 9#, 96, 97, 98, 106 X
g*
RANCHO SECO UNIT 1 e.
TECHNICAL SPECIFICATIONS Surveillance Standards 4.17 STEAM GENERATORS i
ADolicability Applies to inservice inspection of the steam generator tubes.
Obiettive To verify the operability and structural integrity of the tubing as part of the reactor coolant boundary.
Soetification Each steam generator'shall be demonstrated OPERABLE by performance of the fallowing augmented inservice inspection program and the requirements of Specification 1.3.
4.17.1 Steam Generator Samnle Selection and Insoection Steam generator tubing shall be demonstrated OPERABLE by selecting and inspecting steam generators as specified in Table 4.17-1.
4.17.2 Steam Generator Tube Samole Selection and Insoettien The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.17-2A.
The inspection result classification
)
and the corresponding action required for inspection of " specific limited areas" (see paragraph 4.17.2e) shall be as specified in Table 4.17-28.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.17-3 and the inspected tubes shall be verified acceptable per l
Specification 4.17.4.
The tubes selected for these inspections shall include at least 3% of the total number of tubes in both steam generators and be selected on a random basis except:
a.
If experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first sample inspection during inservice inspection (subsequent to the first inservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations D201), and 2.
Special area tubes pursuant to Specification 4.17.4a.6.
l Amendment No.73, 7E, 106 4-51
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.2 (continued) c.
The second and third sample inspections during each inservice inspection may be less than a full tuba inspection by concentrating (selecting at least 50% of the tubes to be inspected) the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
d.
A tub'e inspection (pursuant to Specification 4.17.4.5) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall se selected and subjected to a tube inspection.
C" Adjacent"is Interpreted to mean the nearest tube capable of being Insoected.) Tubes which do not permit passage of the eddy current probe will be considered as degraded tubes when classifying inspection results.
e.
Tubes in specific limited areas which are distinguished by unique operating conditions and/or physical construction (for example, tubes adjacent to the open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled) may be excluded from random samples if all such tubes in the specific area of a steam generator are inspected. No credit will be taken for these tubes in meeting minimum sample size requirements.
The results'6f each sample inspection shall be classified into one of the following three categories:
Cateaorv Impection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 Hore than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the t.bove percentage calculations.
Amendment No. 73, 7f>,106 4-52
1' RANCHO SECO UNIT 1 i
=, -
TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.3 Insoettien Frequencies The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
a.
The first inservice inspection shall be performed during the first refueling outage. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service result in all inspeption results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed
)
degradation has not continued'and no significant additional degradation has occurred, the inspection interval may be i
extended. to a maximum of once per 40 months.
I b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.17-2A and/or Table 4.17-2B-at.40-month intervals falls in Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.17.3a and the interval can be extended to a 40-month period.
c.
Additional, unscheduled inservice inspections shall be performed on cach steam generator in accordance with the first sample inspection specified in Table 4.17-2A during the shutdown subsequent to any of the following conditions:
1.
A seismic occurrence greater than the Operating Basis Earthquake, 2.
A loss-of-coolant accident requiring automatic actuation l
of the engineered safeguards, or 3.
A main steam line or feedwater line break as defined in l
the USAR.
d.
After primary-to-secondary tube leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.1.6.9, an inspection of the affected steam generator will be performed in accordance with the following criteria.
1.
If the leaking tube falls within one of the Special Area groups designated in either Table 4.17-4 or Table 4.17-5, all of the tubes in this group in this steam generator will be inspected.
2.
If the leaking tube does not fall within one of the Special Area groups, an inspection will be performed on the affected steam generator in accordance with Table 4.17-2A with an initial inspection sample size of 6% of the tubes in the affected steam generator.
Amendment No. 73, 76, 106 4-53
RANCHO SECO UNZT 1 TECHN! CAL SPECfffCAT10NS Surveillance Standards 4.17.4 Definitions l
a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication
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drawings or specifications.
Eddy-current testing indications of less than 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of,a tube.
3.
Deoraded Tube means a tube containing imperfections 220%
of the nominal wall thickness caused by degradation.
4.
Defective Tube means a tube containing an imperfection 2.40% of the nominal tube wall thickness unless higher limits are shown acceptable by analysis. Defective tubes shall be plugged.
5.
Tube Insoection means an inspection of the steam generator tube from the point of entry completely to the point of exit (except as noted in 4.17.2c and 4.17.4a.6).
l 6.
Soecial Area Tubes include those tuDes which have shown a significant amount of degradation throughout their operating history. These include peripheral tubes and lane region tubes designated in Tables 4.17-4 and 4.17-5.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions required by Table 4.17-2A (and Table 4.17-2B if provisions of paragraph 4.17.2e are utilized).
4.17.5 Reports a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 30 days.
l b.
The results of the steam generator tube inservice inspection shall be included in a Monthly Operating Report for the period in which this inspection was completed. This report shall include:
Amendment No. 73 EE, 76,106 4-54
3;8
'E RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 1
Surveillance Standards
]
4.17.5 (continued) 1 1.
Number and extent of tubes' inspected.
- 2..
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
c.
Results of steam generator tuba inspections which fall into Category C-3 require notification of the Commission within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and-shall be reported pursuant to Specification 6.9.5P.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent
. recurrence.
4.17.6 OTSG Auxiliary Feedwater Header Surveillance On the first refueling outage following the 1983 refueling outage, and at the 10-year ISI, the following inspections will take place:
a.
Visual inspections of the secured Internal Header, attachment welds and external headers thermal sleeves will be made-through selected openings, and.will be performed in such a manner that the known cracks in the Internal Header will be inspected.
b.
Selecteqspecialinterestperipheraltubes,designatedin Table 4.17-3, will be Eddy Current inspected but shall not be considered a part of the Eddy Current inspection that is conducted pursuant to Technical Specification 4.17.1 through 4.17.5.
4.17.7 Insoection Accentante Criteria and Corrective' Actions a.
Video taped inspections of the known cracks performed during the initial discovery will be compared with the crack configuration found during this surveillance.
This comparison will allow a determination to be made as to whether or not the crack has propagated.
b.
If any inspected special interest peripheral tube indicates clearance (less than 1/4") or greater than 40% through wall indications, it will be plugged.
4.17.8 Renorti A report of these inspections will be prepared and incorporated in the subsequent Monthly Report to the NRC.
Amendment No.73, 66, 76,106 4-55 1
RANCHO SECO UNIT 1 TECHNICAL.5 SPECIFICATIONS Surveillance Standards Bases The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained.
The surveillance requirements of steam generator tubes are based on a modification of B&W - Standard Technical Specifications dated June 1,1976.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is eyidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inseryice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
For example, historical data has shown that certain areas of the steam generators are particularly susceptible to corrosion and degradation. Consequently, the inservice inspection now includes provisions for a more in-depth inspection of a Special Area group of tubes specified in Table 4.17-4 and Table 4.17-5.
Operational experience has shown that tube defects can be the result of unique operating conditions or physical arrangements in certain areas of the steam generators.
A full inspection of all of the tubes in such limited areas will provide complete assurance that degraded or defective tubes in these areas are detected. Because no credit is taken for these distinctive tubes in the constitution of the first sample or its results, the requirements for the first sample are unchanged. This requirement is essentially equivalent to and meets the intent of the requirements set forth in NRC Regulatory Guide 1.83, Revision 1 and does not reduce the margin of safety provided by thos,e, requirements.
Hastage-type defects are unlikely with AVT chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it l
will be found during scheduled inservice steam generator tube examinations.
. Plugging will be required for defective tubes. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 207, of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, the Commission will be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the
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results shall be reported pursuant to Specification 6.9.5P.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy current inspection and revision of the Technical Specifications, if necessary.
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l Amendment No. 73, EE, 76,106 j
4-SSa
RANCHO SECO UNIT 1 l
TECHNICAL SPECIFICATIONS I
Surveillance Standards i
EAin (continued)
The visual and eddy current inspections provide the capability of determining the success of the internal aux feedwater header stabilization by monitoring the long term effects to tube integrity and crack propagation. The inspections will focus on known crack growth, new crack identification (if any), and tube effects in localized areas near the internal header brackets.
Additionally, visual inspection of the external header thermal sleeves will provide assurance that the new design header will not introduce additional problems by demonstrating sleeve integrity.
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.17-4 SPECIAL PERIPHERAL GROUP TUBES (Above and. including the 13th Tube Support Plate ONLY)
Eng Tubes 1
1-16 2
1-27 3
1-34 4
1-41 5
1-17, 30-46 6
1-14, 38-51 7
1-12, 43-54 8
1-10, 48-57~
9 1-10, 53-62 10 1-9, 57-65 11 1-9, 60-68 12 1-9, 63-71 13 1-8, 67-74 14 1-7, 69-75 15 1-7, 72-78 16 1-7, 75-81 17 1-6, 77-82 18 1-7, 79-85 19 1-6, 81-86 20 1-6, 80-85 21 1-6, 85-90 22 1-6, 88-93 23 1-6, 89-94 24 1-5, 91-95 25 1-6, 93-98 26 1-5, 95-99 27 1-5,96-100 28 1-5,97-101 i
29 1-5, 100-104 i
30 1-5, 101-105 l
31 1-5, 102-106 32 1-5, 103-107 33 1-4, 105-108 1
34 1-4, 104-107 1
35 1-4, 105-108 36 1-5, 109-113 37 1-5, 110-114 38 1-5, 111-115 39 1-5, 112-116 40 1-4, 114-117 Amendment No. 106 4-57d
l*
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
+
Surveillance Standards TABLE 4.17-4 (Continued)
SPECIAL PERIPHERAL GROUP TUBES -
(Above and including the 13th Tube Support Plate ONLY)
E2M hhti 41 1-3, 114-116 42 1-3, 115-117 43 1-3, 116-118 s
44 1-3, 117-119 45 1-4, 117-120 46 1-4, 116-119 47 1-4, 119-122 48 1-4, 120-123 49 1-4, 121-124 50 1-3, 121-123 51 1-3, 122-124 52 1-3, 123-125 53 1-3, 124-126 54 1-4, 124-127 55 1-3, 124-125 56 1-3, 125-127 57 1-3, 126-128 58 1-3, 127-129 59 1-3, 122-124 60 1-3, 127-129 61 1-3, 124-126 62 1-2, 128-129 63 3, 126-128 64 124-126 65 123-124 66 125-127 67 127-128 68 126-127 69 128-130 70 128-129 71 127-129 72 127-128 73 126-128 74 122-123 75 123-124 76 58 77 122-124 78 122-124 79 126-128 80 128-129 Amendment No.106 4-57e
o y
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.17-4 (Continued).
SPECIAL PERIPHERAL GROUP TUBES (Above and including the 13th Tube Support Plate'ONLY)
E2M hhfi 81 127-129 82 127-128 83 128-130 84 126-127 85 125-126 86 125-127 87 123-124 88 124-126 89 3 '126-128 90 1-2, 128-129 91 1-3, 124-126 92 1-3, 127-129 93 1-3, 122-124 94 1-3, 127-129 95 1-3, 126-128 96 1-3, 125-127 97 1-3, 124-126 98 1-4, 124-127 99 1-3, 124-126 100 1-3, 123-125 101 1-3, 122-124 102 1-3, 121-123 103 1-4, 121-124 104 1-4, 120-123 105 1-4, 119-122 106 1-4, 116-119 107 1-4, 117-120 108 1-3, 117-119 109 1-3, 116-118 110 1-3, 115-117 111 1-3, 114-116 112 1-4, 114-117 113 1-5, 112-116 114 1-5, 111-115 115 1-5, 110-114 116 1-5, 109-113 117 1-4, 105-108 118 1-4, 104-107 119 1-4, 105-108 120 1-5, 103-107 i
Amendment No.106 4-57f
e.
RANCHO SECO UNIT 1
~*
TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.17-4 -(Continued)
SPECIAL PERIPHERAL GROUP TUBES
'Above and including the 13th Tube Support Plate ONLY)
Ra Tubes 121 1-5, 102-106 122 1-5,~101-105
+
123 1-5, 100-104 5
124 1-5,97-101 125 1-5,96-100 126 1-5, 95-99 127 1-6, 93-98 128 1-5. 91-95 129 1-6,'89-94 130 1-6, 88-93 131 1-6, 85-90 132 1-6, 80-85 133 1-6, 81-86 134 1-7, 79-85 135 1-6, 77-82 136 1-7, 75-81 137 1-7, 72-78,
138 1-7, 69-75 139 1-8, 67-74 140 1-9, 63-71 141 1-9, 60-68 142 1-9. 57-65 143 1-10, 53-62 144 1-10, 48-57 145 1-12, 43-54 146 1-14, 38-51 147 1-17, 30-46 148 1-41 149 1-34 150 1-27 151 1-16 Amendment No.106 4-57g
mm.
l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.17-5 SPECIAL LANE REGION GROUP TUBES (Above and including the 14th Tube Support Plate ONLY)
En Lhti 63 1-2~
64 1-4 65 1-6 66 1-9 67 1-13 68 1-20 69 1-20 70 1-23
~
71 1-27 72 1-30 73 1-60 74 1-60 75 1-60 77 1-60 78
'1-60 79 1-60 80 1-30 81 1-28 82 1-23 83 1-20 84 1-20 85 1-13 86 1-9 87 1-6 88 1-4
~
89 1-2 Amendment No. 106 4-57h
_