RBG-46981, Correction of Technical Specification Typographical Errors
ML093380291 | |
Person / Time | |
---|---|
Site: | River Bend ![]() |
Issue date: | 11/30/2009 |
From: | Lorfing D Entergy Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RBF1-09-0165, RBG-46981 | |
Download: ML093380291 (9) | |
Text
SEntergy Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225381 4157 Fax 225 635 5068 dlorfin@entergy.com David N. Lorfing Manager-Licensing RBG-46981 November 30, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
REFERENCES:
Correction of Technical Specification Typographical Errors River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47
- 1. Issuance of Amendment No. 165 to Facility Operating License No. NPF-47, River Bend Station (TAC No. ME0406),
dated August 11, 2009
- 2. Issuance of Amendment No. 166 to Facility Operating License No. NPF-47, River Bend Station (TAC No. ME0157),
dated September 29, 2009
- 3. Proposed Guidance for Correction of Technical Specification Typographical Errors, SECY-96-238, dated November 19, 1996 RBF1-09-0165
Dear Sir or Madam:
This letter requests NRC approval of corrections of two typographical errors in the River Bend Station Technical Specifications.
These errors were inadvertently introduced during the final processing of License Amendments 165 and 166 (References 1 and 2). These errors were neither addressed in the notice to the public nor reviewed by the NRC, and, thus, fall within the scope of the guidance provided by SECY-96-238 (Reference 3). describes the typographical errors and corrections. Attachment 2 contains mark-ups of the affected Technical Specification pages. Attachment 3 contains corrected pages.
RBG-46981 November 30, 2009 Page 2 of 2 If you have any questions, please contact me at 225-381-4157.
Sincerely, David N. Lorfing Manager - Licensing - Description of Technical Specification Typographical Errors - Marked Up Technical Specification Pages Correcting Typographical Errors - Revised Technical Specification Pages cc:
Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Resident Inspector River Bend Station Mr. Alan B. Wang, Project Manager U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G14 11555 Rockville Pike Rockville, MD 20852-2738
ATTACHMENT 1 DESCRIPTION OF TECHNICAL SPECIFICATION TYPOGRAPHICAL ERRORS
- 1. Requested Action Consistent with the information contained in SECY-96-238, River Bend Station is requesting corrections of two typographical errors that were inadvertently introduced into the station's Technical Specifications (TS). The marked up TS pages included in the original applications for license amendment were correct.
The errors were introduced by the River Bend staff in development of the revised.
pages supplied to NRC for issuance with the amendment approval letter. The requested corrections are intended to restore the affected pages to the condition intended by the amendment applications.
- 2. Typographical Errors The specific details of the typographical errors are as follows:
- a. TS page 3.8-10 Amendment No. 165 approved Surveillance Requirement (SR) 3.8.1.12(c) to read:
"Achieves steady state voltage > 3740 and < 4580 V and frequency
> 58.8 Hz and < 61.2, Hz; and" The symbol "V" should be inserted after the number "3740."
- b. TS page 5.0-19 Amendment No. 166 approved TS 5.6.5 to add a new sub-bullet number 25, which reads:
"NEDC-33383P, 'GEXL97 Correlation to ATRIUM-10 Fuel,' Global Nuclear Fuel."
The word "Applicable" should be inserted following the word "Correlation."
- 3. Corrections to Affected Pages SECY-96-238 (Reference 3) provides guidance to correct inadvertent typographical errors in the Technical Specifications. The errors described above were neither posted in the public notices nor were they reviewed by NRC as part of the license amendment process. Therefore, they may be corrected without a license amendment.
ATTACHMENT 2 MARKED UP TECHNICAL SPECIFICATION PAGES CORRECTING TYPOGRAPHICAL ERRORS TS page 3.8-10 TS page 5.0-19
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE
)
FREQUENCY SR 3.8.1.12 NOTES
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
This Surveillance shall not be performed in MODE 1 or 2. (Not applicable to DG 1 C) '
However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated Emergency Core 18 months Cooling System (ECCS) initiation signal each DG auto-starts from standby condition and:
- a.
For DG 1C during the auto-start maintains voltage _< 5400 V and frequency _< 66.75 Hz;
- b.
In< 10 seconds for DG 1Aand DG 1B and
_: 13 seconds for DG 1C after auto-start and during tests, achieves voltage Ž 3740 V and frequency > 58.8 Hz.
- c.
Achieves steady state voltage > 3740 ad
< 4580 V and frequency > 58.8 Hz and
- 61.2 Hz; and
- d.
Operates for > 5 minutes.
(continued)
RIVER BEND 3.8-10 Amendment No. 9! 121 133, 165
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 24)
NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR-Il)".
- 25)
NEDC-33383P, "GEXL97 Correlation to ATRIUM-10 Fuel," Global Nuclear Fuel.
- c.
The core operating limits shall be determi ed such that all applicable limits (e.g., fuel thermal mechanical limits core thermal hydraulic limits, Emergency Core Cooling Systems (ECC ) limits, nuclear limits such as SDM, transient analysis limits, and acci ent analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle re /isions or supplements, shall be provided upon issuance for each rel d cycle to the NRC.
CApplicable RIVER BEND 5.0-19 Amendment No. 81 96 99 100 105 106 4-22, 166
ATTACHMENT 3 REVISED TECHNICAL SPECIFICATION PAGES TS page 3.8-10 TS page 5.0-19
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.12
NOTES--------------
- 1.
All DG starts may be preceded by an engine prelube period.
- 2.
This Surveillance shall not be performed in MODE 1 or 2. (Not applicable to DG 1C)
However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated Emergency Core 18 months Cooling System (ECCS) initiation signal each DG auto-starts from standby condition and:
- a.
For DG 1C during the auto-start maintains voltage < 5400 V and frequency < 66.75 Hz;
- b.
In _< 10 seconds for DG 1A and DG 1B and
< 13 seconds for DG 1C after auto-start and during tests, achieves voltage > 3740 V and frequency _> 58.8 Hz.
- c.
Achieves steady state voltage > 3740 V and
_ 4580 V and frequency >_ 58.8 Hz and
- 61.2 Hz; and
- d.
Operates for >_ 5 minutes.
(continued)
RIVER BEND 3.8-10 Amendment No. 81 -2 2133, 165
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 24)
NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR-II)".
- 25)
NEDC-33383P, "GEXL97 Correlation Applicable to ATRIUM-10 Fuel," Global NuclearFuel.
- c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
RIVER BEND 5.0-19 Amendment No. 81 96 99 100 105 106 4-22, 166