ML13101A369
| ML13101A369 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/16/2013 |
| From: | Billoch-Colon A Plant Licensing Branch II |
| To: | William Gideon Carolina Power & Light Co |
| Billoch-Colon A NRR/DORL/LPL2-2 | |
| References | |
| TAC ME8844 | |
| Download: ML13101A369 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 16, 2013 Mr. William G. Gideon, Vice President H. B. Robinson Steam Electric Plant Carolina Power & Light Company 3581 West Entrance Road Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 - ISSUANCE OF AN AMENDMENT ON TECHNICAL SPECIFICATION CHANGES REGARDING AN ADDITION OF A NOTE TO LIMITING CONDITIONS FOR OPERATION 3.1.4 AND 3.1.7 ALLOWING 1-HOUR SOAK TIME (TAC NO. ME8844)
Dear Mr. Gideon:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 233 to Renewed Facility Operating License No. DPR-23 for the H. 8. Robinson Steam Electric Plant, Unit No.2 (HBRSEP). This amendment changes the HBRSEP Technical Specifications (TSs) in response to your application dated June 8, 2012 (Agencywide Documents Access and Management System Accession No. ML12172A260), as supplemented by letters dated, October 12, 2012 (ML12298A359), October 22,2012 (ML12310A085), and April 24, 2013 (ML13128A072).
The amendment changes HBRSEP TSs to add a 1-hour soak time to Limiting Conditions for Operation 3.1.4 and 3.1.7 allowing the control rod drive mechanisms additional time following substantial rod motion to reach thermal equilibrium.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. Amendment No.233 to DPR-23
- 2. Safety Evaluation cc w/enclosures: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 233 Renewed License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power & Light Company (the licensee), dated June 8,2012, as supplemented by letters dated October 12, 2012, October 22,2012, and April 24, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (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 the 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 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.
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 233 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 120 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to Operating License No. DPR-23 and the Technical Specifications Date of Issuance: May 16, 2013
ATTACHMENT TO LICENSE AMENDMENT NO.233 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Renewed Facility Operating License and Appendix "A>>
Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License DPR-23 License DPR-23 Page 3 Page 3 TSs TSs 3.1-6 3.1-6 3.1-15 3.1-15
- 3 neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by operation of the facility.
- 3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 233 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.
Renewed Facility Operating License No. DPR-23 Amendment No. 233
Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.
AND Individual indicated rod positions shall be as follows:
- a. For bank demand positions;::: 200 steps, each rod shall be within 15 inches of its bank demand position, and
- b. For bank demand positions < 200 steps, each rod shall be within 7.5 inches of the average of the individual rod positions in the bank.
I\J OTE ----------------------------------------------
Individual RPls may be outside their limits for::;;1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following substantial rod movement.
APPLICABILITY: MODES 1 and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inoperable. the limits provided in the COLR.
A.1.2 Initiate boration to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore SDM to within limit.
AND A.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued)
HBRSEP Unit No.2 3.1-6 Amendment No. 233
Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Analog Rod Position Indication (ARPI) System and the Demand Position Indication System shall be OPERABLE.
Note----------------------------------------------
Individual Rod Position Indicators may be outside their limits for::;;1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following substantial rod movement.
APPLICABILITY: MODES 1 and 2.
ACTIONS
NOT E -----------------------------------------------------------
Separate Condition entry is allowed for each inoperable rod position indicator per group and each demand position indicator per bank.
CONDITION REQUIRED ACTION COMPLETION TIME A. One ARPI per group inoperable for one or more A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> groups. rods with inoperable position indicators by using movable incore detectors.
OR A.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to ::;;50% RTP.
B. One or more rods with B.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position rods with inoperable indicators have been position indicators by moved in excess of using movable incore 24 steps in one direction detectors.
since the last determination of the rod's OR position.
(continued)
HBRSEP Unit No.2 3.1-15 Amendment No. 233
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- "" SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 233TO RENEWED FACILITY OPERATING LICENSE NO. DPR-23 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-261
1.0 INTRODUCTION
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 8,2012 (Agencywide Documents Access and Management System Accession No. ML12172A260), as supplemented by letters dated October 12,2012 (ML12298A359), October 22,2012 (ML1231 OA085) , and April 24, 2013 (ML13128A072). Carolina Power & Light Company (the licensee), doing business as Progress Energy Carolinas, Inc., submitted a license amendment request for changes to the H. B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP, the licensee), Technical Specifications (TSs) 3.1.4, "Rod Group Alignment Limits," and TS 3.1 7, "Reactivity Control Systems." The requested change would add a note allowing 1-hour soak time to the Limiting Conditions for Operation (LCOs) 3.1.4 and 3.1.7 following substantial rod motion.
The supplements dated October 12,2012, October 22,2012, and April 24, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's initial proposed no significant hazards consideration determination as published in the Federal Register on August 7,2012 (77 FR 47126). The Ocotber 12,2012, and April 24, 2013, supplements included corrections of typographical errors in earlier submittals.
2.0 REGULATORY EVALUATION
The purpose of the rod control system is to control the motion of the neutron absorbing full length rods. This control system moves the rods in response to demand signals from either the reactor operator (for start-up, shutdown, and power operations), or from the automatic rod control system (power operations) to maintain a programmed reactor coolant system average temperature. It also releases the rods in response to manual or automatic reactor trip signals, allowing the rods to fall into the core, shutting down the reactor.
The purpose of the rod position indication system is to provide indication of actual and demanded control rod positions. In addition, this system provides alarms to alert the reactor operator to misaligned rods, or to the fact that the required shutdown margin is not available due to excessive rod insertion. There are two types of individual rod position indications found in
-2 HBRSEP as stated in the Updated Final Safety Analysis Report (UFSAR) Section 7.7.1.1.5, the analog system and the digital system that serve as backup for each other.
The analog individual rod position indication (IRPI) system furnishes an indication of the actual position each rod has assumed in response to the rod control system command signals. The digital rod position indication system continuously senses and displays rod position information for each rod (control and shutdown).
Section 182a of the Atomic Energy Act requires nuclear power plant operating licenses to include TSs as part of any license. The NRC regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (10 CFR), Part 50, Section 50.36, "Technical Specifications." The TS requirements in 10 CFR 50.36 include the following categories: 1) safety limits, limiting safety systems settings and control settings; 2) limiting conditions for operation; 3) surveillance requirements; 4) design features;
- 5) administrative controls; 6) decommissioning; 7) initial notification; and 8) written reports.
The generic design criteria (GDC), published in 10 CFR Part 50, Appendix A, were not yet available at the time HBRSEP was licensed to operate in July 1970. HBRSEP was designed and licensed according to the proposed 1967 GDC, as stated in the HBRSEP UFSAR Section 3.1.2.
The NRC's acceptance criteria are based on the GDC 6 and 14 in HBRSEP UFSAR as follows:
For HBRSEP GDC 6, the UFSAR Section 3.1.2.6, "Reactor Core Design," states that "the reactor core with its related controls and protection systems shall be designed to function through its design lifetime without exceeding acceptable fuel damage limits which have been stipulated and justified." It also states that "the core and related auxiliary systems designs shall provide this integrity under all expected conditions of normal operation with appropriate margins for uncertainties and specified transient conditions which can be anticipated."
HBRSEP UFSAR Section 3.1.2.14, "Core Protection System," states that "core protection systems, together with associated equipment, shall be designed to prevent or to suppress conditions that could result in exceeding acceptable fuel damage limits."
The NRC staff reviewed the licensee TS changes request to ensure that the proposed changes are consistent with these UFSAR sections and provide reasonable assurance that the control rods would continue to be capable of performing their safety function and the acceptable fuel damage limits would not be exceeded.
3.0 TECHNICAL EVALUATION
The licensee stated that when control rods have been moved substantially, the rod position indicators will often differ from the demand position indication by more than the allowed limits of TSs 3.1.4 and 3.1.7. The1icensee has attributed this difficulty to thermal instabilities that affect the accuracy of the instrumentation system. In these conditions, the indication system incorrectly reports a misalignment. The licensee confirmed that the rods are actually aligned following a brief soak time wherein the analog rod position instrumentation returns to thermal equilibrium and its indication agrees with the demand position indication.
- 3 The licensee proposed to add a note allowing 1-hour soak time to TS LCO 3.1.4 and TS LCO 3.1.7. The proposed 1-hour soak time would allow the control rod drive shaft additional time, following substantial rod motion, to reach thermal equilibrium and the rod position indicators to stabilize within the TS limits. The proposed TS changes are to reduce the operator burden of entering LCO action statements when it is clear that the deviation of the control rod position indications is related to thermal transient effects following rod movement.
The NRC staff reviewed the TS changes, the associated supporting analysis in the licensee's application dated June 8, 2012, as supplemented by letters dated October 12, 2012, October 22, 2012, and April 24, 2013. The NRC staff reviewed the licensee's application to evaluate whether the licensee's analyses and procedures provided reasonable assurance that adequate safety margins can be maintained for the proposed TS conditions.
HBRSEP current TS 3.1.4 requires the positions of reactor control rods to be within alignment limits. Specifically, when bank demand positions are equal to or greater than 200 steps, each control rod shall be within 15 inches of its demand position indication, or 7.5 inches of its demand position indication when bank demand positions are less than 200 steps.
HBRSEP current TS 3.1.7 requires verification that the indication of each Analog Rod Position Indicator (ARPI) is within these same TS 3.1.4 limits for the control rods to be considered properly aligned. Specifically, Surveillance Requirement (SR) 3.1.7.2 requires verification that each ARPI is within 7.5 inches of the average of the individual ARPls in the associated bank after moving each full length rod cluster control assembly (RCCA) bank greater than or equal to 19 steps and returning the banks to their original positions when the bank position is less than 200 steps withdrawn. Similarly, SR 3.1.7.3 requires verification that each ARPI is within 15 inches of the associated bank demand position after moving each full length RCCA bank greater than or equal to 19 steps and returning the banks to their original positions when the bank positions are greater than or equal to 200 steps withdrawn. Agreement between the ARPI indication and the demand position indication assures that the ARPI is functioning properly.
The licensee proposed TS changes would allow a 1-hour soak time, during which the ARPI may falsely indicate that reactor control rods are not within their TS-required deviation limits. During the soak-time period, the ARPI may indicate misalignment despite the rods actually being within their alignment limits. This soak time allows the ARPI system to return to thermal equilibrium and indicate the actual position.
If the control rods are not properly aligned, current TS 3.1.7, Action A requires the licensee to verify, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the position of the rods using the movable incore detectors. The proposed changes would potentially allow a misaligned rod to go undetected for an additional hour (from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />). This is the time that individual ARPI instrumentation could be inoperable or rod could be misaligned before TS required actions would be implemented.
3.1 Safety Analyses In support of its TS changes, the licensee referenced, in its June 08,2012, submittal, the existing safety analysis in the HBRSEP UFSAR Section 15.4.3, which considers two types of misalignment events: static misalignment of a single RCCA and a dropped RCCA.
-4 The static misalignment analysis in UFSAR Section 15.4.3.2 considers two limiting cases that bound the misalignment conditions: one case assumes that with Bank D at its TS insertion limit, the most reactive "D" bank RCCA is fully withdrawn from the core; and the second case assumes that with all Banks fully withdrawn, the most reactive RCCA is fully inserted to the bottom of the core. The results of the analysis show that the safety limit of the departure from nucleate boiling ratio (DNBR) is satisfied, assuring no failure of fuel pin during the static misalignment events.
The analysis of the dropped rod event in UFSAR Section 15.4.3.3 is initiated from a dropped RCCA. The results of the analysis show that for the case of a dropped full-length RCCA or RCCA bank, the minimum calculated DNBR is greater than the safety limit; and the peak linear heat generation rate is less than the fuel centerline melting limit, meeting the acceptance criteria on DNBR and fuel centerline melt and assuring no fuel failure.
For the analyses of both the misalignment of a single RCCA event and the dropped RCCA event, the licensee does not credit operator actions. Thus, the NRC staff concludes that both events are not time-dependent and the additional hour while a misaligned RCCA may be undetected would not increase the consequences of the misalignment and dropped RCCA events.
3.2 Plant Controls and Procedures In response to the NRC staff's request, the licensee's October 22,2012, supplemental letter, provided additional information that described the procedures in place to ensure the operators would promptly identify any rod misaligned. The plant specific procedures in HBRSEP direct operators to use the Emergency Response Facility Information System (ERFIS) to monitor control rod positions. The safety parameters display system alarm screen of the ERFIS identifies degrading equipment or plant conditions prior to main control room alarms, or system transients.
The ERFIS rod misalignment program monitors rod alignment whenever the reactor trip breakers are shut, and automatically prints out alarm related to information concerning rod position deviation, misalignment, and overlap sequence every 10 minutes when off-normal conditions exists.
Additionally, the abnormal operating procedures for the reactor control system provides a list of symptoms or a misaligned rod, stuck rod, or IRPI failure and required operator response for each condition with direction that if there is any doubt as to IRPI failure or actual rod misalignment then rod misalignment is to be assumed. The licensee stated that there is a plant specific operating procedure that can be used to determine the position of a control rod when operating above power levels (listed in the LCO action statement) at which control rod misalignment may impact the validity of the safety analyses. The procedure utilizes the movable incore detector system to determine the control rod position by measuring flux traces.
The traces are reviewed to determine the actual control rod position.
The licensee stated that the plant and abnormal operating procedures discussed above will be revised to provide additional guidance regarding the use of the 1-hour soak time and will continue to be used when the proposed TS changes (if approved) are implemented. The NRC staff finds that the licensee's procedures provide reasonable assurance that the operators will
-5 identify a misaligned control rod during the 1-hour soak time.
Because the licensee's analyses demonstrate that misaligned rod and dropped rod events are not time-dependent, and neither the consequences nor the probability of these events would increase during the proposed 1-hour soak time, the NRC staff concludes that the proposed TSs changes would not increase the risk to the public health and safety. Also, the NRC staff finds that appropriate operator actions, as described in the HBRSEP procedures, would provide a high probability of identifying any misaligned rods during the proposed 1-hour soak time.
The NRC staff reviewed the effects of the proposed changes against HBRSEP GDC 6 and 14 in HBRSEP UFSAR Section 3.1.2. The NRC staff finds that the addition of a note allowing a 1-hour soak-time to LCOs 3.1.4 and 3.1.7 meets GDC 6 and 14. The proposed changes meet GDC 6 because the changes would not adversely affect the ability of the operators and the reactor protection system to adequately protect both HBRSEP and the public. The proposed change does not alter the design, function, or operation of any HBRSEP components. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of the proposed changes. Additionally, the proposed change will not prevent the reactivity protection system, from performing its intended function and the acceptable fuel damage limits will not be exceeded. Hence, HBRSEP would continue to meet GDC 6 and 14, respectively. The NRC staff concludes the licensee's analyses demonstrate (1) that the misaligned rod and dropped rod events are not time-dependent, (2) that adequate safety margins can be maintain, and (3) that appropriate operator actions, as described in the HBRSEP procedures, would provide a high probability of identifying any misaligned rods during the proposed 1-hour soak time. Therefore, the NRC staff finds the proposed TSs changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of South Carolina official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no Significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (77 FR 47126). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by
- 6 operation in the proposed manner, (2) there is reasonable assurance that that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Sun Date: May 16, 2013
May 16, 2013 Mr. William G. Gideon, Vice President H. B. Robinson Steam Electric Plant Carolina Power & Light Company 3581 West Entrance Road Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 - ISSUANCE OF AN AMENDMENT ON TECHNICAL SPECIFICATION CHANGES REGARDING AN ADDITION OF A NOTE TO LIMITING CONDITIONS FOR OPERATION 3.1.4 AND 3.1.7 ALLOWING 1-HOUR SOAK TIME (TAC NO. ME8844)
Dear Mr. Gideon:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 233 to Renewed Facility Operating License No. DPR-23 for the H. B. Robinson Steam Electric Plant, Unit No.2 (HBRSEP). This amendment changes the HBRSEP Technical Specifications (TSs) in response to your application dated June 8, 2012 (Agencywide Documents Access and Management System Accession No. ML12172A260), as supplemented by letters dated, October 12,2012 (ML12298A359), October 22,2012 (ML12310A085), and April 24, 2013 (ML13128A072).
The amendment changes HBRSEP TSs to add a 1-hour soak time to Limiting Conditions for Operation 3.1.4 and 3.1.7 allowing the control rod drive mechanisms additional time following substantial rod motion to reach thermal equilibrium.
A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA!
Araceli T. Billoch Col6n, Project Manager Plant Licensing Branch 1\-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosures:
- 1. Amendment No. 233 to DPR-23
- 2. Safety Evaluation cc w/enclosures: Distribution via ListServ DISTRIBUTION:
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