ML20247B682
| ML20247B682 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/19/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247B408 | List: |
| References | |
| NUDOCS 8907240177 | |
| Download: ML20247B682 (4) | |
Text
1 RANCHO SECO UN8T 1 i
TECHN3 CAL SPECfF2 CAT 80NS L2ST OF iASLES (Centinued)
L'le D
4.1-2 MINI M EQUIPMENT TEST FREQUEEY 44
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4.1-3 MINIM SAMPLIfG FREQUEEY 44 4.6-1 DIESEL GENERATDR TEST SCHEDULE 4-34j i
4.6-2 ADDITI0fML RELIABILITY ACTIOf6 4-34k 4.14-1 DELETED
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i 4.17-1 HINIKJM NUMSER OF STEAM GENERATORS 70 BE INSPECTED.
4-56 i
DURING INSEkVICE INSPECTION l
i 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENEPATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-576.c 4.17-4 SPECIAL PERIPHERAL GROUP TUBES 4-57d-g i
4.17 5 SPECIAL LANE REGION GROUP TUBES 1
4-57h I
4.19-1 RADIOACTIVE LIOJID EFFLUENT K)NITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS s
i
'4.20-1 RADI0 ACTIVE CASE 005 EFFLUENT HJNITORING INSTRUMENTATION 4-66 l
SURVEILLANCE REQUIREMENTS i
4.21-1 RADIOACTIVE LIQUID RASTE SAMPLING. AND ANALYSIS PROGRAM 4-70 lI l
1 i -
4.21-2 RADIOACTIVE LIQUID RASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADIOACTIVE GASE0V$ WASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 HAXIKJM VALUES FOR THE LOMER LIMITS OF DETECTION (LLD) 4-64 4.28-1 EXPLOSIVE CAS HIXTURE INSTRUMENTATION SURVEILLANCE l
4-EB REQUIREMENTS 4.34-1 METEOROLOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 MINIMUM SHIFT CREW COMPOSITION 6-2 Amendment No. 28. f 6. 76. 88. Pl. PE. 97, 98,106,110 8907240177 890719 PDR ADOCK 05000312 P
x PDC
j RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i
s I
Surveillance Standards 4.17 STEAM GENERATOR 9 s
Aeolicability Applies to inservice inspection of the steam generator tubes.
Obiective To verify the operability and structural integrity of the tubing as part of the reactor coolant boundary.
l Specification Each steam generator sNall be demonstrated OPERABLE by performance of the following augmented it. service inspection program and the requirements of Specification 1.3.
4.17.1 Steam Generator Samole Selection and Inspection 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 Insoection The steam generator tube minimum sample size, inspection result l
classification, and the corresponding action required shall be as I
specified in Table 4.17-2A.
The inspettion result classification and the corresponding action required for inspection of " specific limited areas" (see paragraph 4.17.2e) shall be as specified in Table 4.17-2B.
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 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 tubes that previously had detecta.ble wall penetrations (>201), that have not been plugged or sleeve repaired in the affected area, l
l l
2.
All sleeves that previously had detectable wall penetrations (>20%) that have not been plugged, and i
Amendment No. 72, 76, 106, 109 i
4-51 l
I i
RANCHO SECO UNIT 1 l
TECHN8 CAL SPECIFICATIONS Surveillance Standards 4.17.5 (continued) 1.
Number and extent of tubes inspected.
4 2.
Location and perce?t of wall-thickness penetration for each indication of an imperfection.
I 3.
Identification of tubes plugged.
I c.
Results of steam generator tube inspections which fall into.
Category C-3 require notification of the Commission within 4 1
hours 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 Auriliarv Feedwater Header Surveillance I
On the first refueling outage following the 1983 refueling outage, and at the 10-year ISI, the following inspe-tions will take place:
a.
Visual inspections of the secured Internal Header, attachment
- sids 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.
Selectec Table 4.j special interest peripheral tubes, designated in 17-3, will be Eddy Current inspected but shall not be considered a part of the Eddy Current insp3ction that is conducted pursuant to Technical Specification 4.17.1 through 4.17.5.
4.17.7 Intrettien Accertence Criteria and Corrective' Actions c.
Video tared 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 Recorts l
A report of these inspections will be prepared and incorporated in the subsequent Monthly Report to the NRC.
Amendment No.73, EE, 7E,106 4-55
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