ML17251A649
| ML17251A649 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/17/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8604230133 | |
| Download: ML17251A649 (14) | |
Text
REGULATOR NFORNATION DISTRIBUTION'EN (R IDS)
ACCESSION NBR: 8604230133 DOC, DATE: 86/04/17 NOTARIZED:
NO DOCKET ¹ FACIL:50-244 Robert-Emmet Qinna Nuclear Planti Unit 1. Rochester G
05000244 AUTH. MANE AUTHOR AFFILIATION KOBERi R. W.
Rochester Qas 8c Electric Corp.
REC IP. NANE RECIPIENT AFFILIATION
'LEARN Q. E.
PWR Prospect Directorate 1
SUBJECT:
Forwards revised Tech Spec pagesi per Nov 1981 proposed amend to License DPR-18'eleting bg-item listing oF snubbers. Revised submittal contains only minor nonsafetg-related format changes re snubber insp requirements.
DISTRIBUTION CODE:
A047D COPIES RECEIVED: LTR ENCL SI ZE:
TITLE:
OR Submittal:
Inservice Inspection/Testing NOTES: License Exp date in accordance with 10CFR2i 2. 109(9/19/72).
05000244 REC IP IENT ID CODE/NAME PWR-A EB FAIRTILE>N INTERNAL: ADN/LFNB NRR BWR ADTS NRR PWR-A ADTS NRR PWR-B ADTS NR
/EIB L
04 COPIES LTTR ENCL 1
1 1
1 1
0 1
1 1
1 1
1 1
1 1
1 REC IPIENT ID CODE/NAME PWR-* PD1 PD 01 ELD/HDS4 NRR BWR EB NRR PWR-A EB NRR PWR-B EB NRR/TANB RQN1 COP IES LTTR ENCL 5
5 EXTERNAL: 24X NRC PDR 02 1
1 1
LPDR NSIC 03 05 TOTAL NUBBER OF COPIES REQUIRED'TTR 23 ENCL 21
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zzuzizs rizzzzizl III'S IIIZ@Z IIIIII ZuIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 ROGER W. KO8ER Vee PRCSIDCNT ELECTRIC IN STEAM PRODUCTION TCLCPHONC ARcA coDc 7IS 546.2700 April 17, 1986 Director of Nuclear Reactor Regulation Attention:
Hr. George E. Leari Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
Deletion of Snubbers from Technical Specifications R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Nr. Lear:
In November
- 1981, Rochester Gas and Electric submitted a
proposed amendment to Ginna's Technical Specifications deleting the by-item listing of snubbers.
The safety analysis attached to the submittal discussed the incorporation of the list and specific snubber inspection requirements into the Ginna In-Service Inspection Program.
This proposed amendment was noticed for public comment in the Federal Register citation 48FR164 dated August 23, 1983.
With this letter are provided the current amended pages to the Technical Specifications which incorporate the 1981 proposed changes for snubbers.
The differences between these proposed pages and the originals submitted in 1981 are minor and non-safety related and reflect only format changes.
The nature of these changes does not require a
no significant hazards determination and the safety analysis submitted in 1981 is still applicable.
V y truly yoursi 0
4J Ro er W. Kober Bb04230133 Sb0417 PDR ADDCR 00000244 P
pDR I gI
Attach'ment A
Remove Insert Page ii Page 3.13-1 through 3.13-7 Page 4.2-1 through 4.2-2 Page 4.14-1 through 4.14-5 Page ii Page 3.13-1 Page 4.2-1 through 4.2-3 Page 4.14-1 Page 6.10-3
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TABLE OF CONTENTS (cont'd) 5.0 4.8 4 9 4.10 4.11 4.12 4.13 4.14 4.15 4.16 DESIGN Auxiliary Feedwater System Reactivity Anomalies Environmental Radiation Survey Refueling Effluent Surveillance Radioactive Material Source Leakage Test (Deleted)
Fire Suppression System Test Overpressure Protection System FEATURES Pacae 4.8-1 4.9-1 4.10-1 4.11-1 4.12-1 4.13-1 4 14 1
I 4.15-1 4.16-1 5.1 5.2 5.3 5.4 5.5 Site Containment Design Features Reactor Design Features Fuel Storage Waste Treatment Systems 5.1-1 5.2-1 5.3-1 5.4-1 5.5-1 6.0 ADMINISTRATIVE CONTROLS 6.1 6.2 6.3 6.4 6.5
.Responsibility Organization 6.2.1 Offsite 6.2.2 Facility Staff Station Staff Qualification Training Review and Audit 6.5.1 Plant Operations Review Committee (PORC) 6.5.2 Nuclear Safety Audit and Review Board (NSARB) 6.1-1 6.2-1
- 6. 2-1 6.2-1 6.3-1 6.4-1 6.5-1 6.5-1 6.5-5 6.6 6.7 6.8 6.9 6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17 6.5.3 Quality Assurance Group Reportable Event Action Safety Limit Violation Procedures Reporting Requirements 6.9.1 Routine Reports 6.9.2 Unique Reporting Requirem Record Retention Radiation Protection Program (Deleted)
High Radiation Area (Deleted)
Offsite Dose Calculation Manual Process Control Program Major Changes to Radioactive Waste Trea tment Systems ents 6.5-11 6.6-1 6.7-1 6.8-1 6.9-1 6.9-1 6.9-3 6.10-1 6.11-1 6.13-1 6.15-1 6.16-1 6.17-1 Amendment No.
Proposed
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3.13 Snubbers A licabilit Applies to the operability of all safety-related snubbers listed in the Inservice Inspection Program.
Ob-ective To specify the requirements for operability of snubbers.
S ecification 3.13.1 3'3',
Whenever the reactor is above cold shutdown, all snubbers listed in the Inservice Inspection Program shall be operable.
In addition, snubbers which support components which are required to be operable at cold or refueling shutdown shall be operable.
If one or more snubbers are inoperable when required to be operable, then restore the inoperable snubber(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the supported component inoperable and take the appropriate actions for that system.
Basis Snubbers are required to be operable to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
3 ~ 1 3 1
Proposed
4.2 Inservice Ins ection A licabilit Applies to the inservice inspection of Quality Groups A, B, and C Components, High Energy Piping Outside of Containment, Steam Generator
- Tubes, and Snubbers. It also applies to inservice pump and valve testing.
4.2.1 To provide assurance of the continuing structural and operational integrity of the structures, components t
and systems in accordance with the requirements of 10CFR 50.55a(g).
S ecification The inservice inspection program for Quality Groups A,
B, and C components, High Energy Piping Outside of Containment and Steam Generator tubes and snubbers shall be in accordance with Appendix B of the Ginna Station Quality Assurance Manual.
The inservice pump and valve testing program shall be in accordance with Appendix C of the Ginna Station Quality Assurance Manual.
These inservice inspection programs shall define the specific requirements of the edition and Addenda of the ASME Boiler and Pressure Vessel
- Code,Section XI, which are applicable for the forty month period of the ten year inspection interval.
The programs'en year inspection intervals shall be based on the following commencing dates.
4.2-1 Amendment No. p Proposed
The inspection interval for Quality Group A components shall be ten year intervals of service commencing on January 1, 1970.
The inspection intervals for Quality Group B and C
Components shall be ten year intervals of service commencing May 1, 1973, January 1, 1980,
- 1990, and 2000, respectively.
The inspection intervals for the High Energy Piping t
Outside of Containment shall be ten year intervals of service commencing May 1, 1973, January 1, 1980,
- 1990, and 2000, respectively.
The inspection program during each third of the first inspection interval provides for examination of all welds at design basis break locations and one-third of all welds at locations where a weld failure would result in unacceptable consequences.
During each succeeding inspection interval, the program shall provide for an examination of each of the design basis break location welds, and each of the welds at locations where a weld failure would result in unacceptable consequences.
The inspection intervals for Steam Generator Tubes shall be specified in the "Inservice Inspection Program" for the applicable forty month period commencing with May 1, 1973.
Inservice Inspection of ASME Code Class 1, Class 2,
and Class 3 components (Quality Groups A, B, and C) 4.2-2 Amendment No. p Proposed
shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
4.2.1.6 The inspection interval for the Inservice Pump and Valve Testing Program shall be ten year intervals commencing with January 1, 1981,
- 1990, and 2000.
4.2.1.7 The inspection intervals for snubbers shall be as specified in the Inservice Inspection Program.
Basis:
The inservice inspection programs provide assurance for the continued structural integrity of the structures, components and systems of Ginna Station.
The programs comply with the ASME Boiler and Pressure Vessel Code Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components" as practicable, with due consideration to the design and physical access of the structures, components and systems as manufactured and constructed.
This compliance will constitute an acceptable basis for satisfying the requirements of General Design Criterion 32, Appendix A of 10 CFR Part 50 and the requirements of Section 50.55a, paragraph g
of 10 CFR Part 50.
- 4. 2-3 Proposed
Deleted 4.14-1 Proposed
m.
Records of the service lives of all hydraulic and mechanical snubbers listed in the Inservice Inspection Program including the date at which the service life commences and associated installation and maintenance records.
6.10-3 Proposed
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