View source for NL-17-0841, Correction of Technical Specification Typographical Error

{{Adams
| number = ML17130A992
| issue date = 05/10/2017
| title = Correction of Technical Specification Typographical Error
| author name = Hutto J
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000366
| license number = 
| contact person = 
| case reference number = NL-17-0841
| document type = Letter type:NL, Technical Specifications
| page count = 8
}}

=Text=
{{#Wiki_filter:~ Southern Nuclear                                    J. J. Hutto Regulatory Affairs Director
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20:" 99.2 5H72              ld 20:\ \l1)2 -;r,o i          fa x jjhutto(ri ''Hltht:m l.*n. ~om MAY 1 0 2017 Docket Nos.: 50-366                                                                NL-17-0841 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error

==References:==
: 1. Joseph M. Farley Nyclear Plant, Units 1 and 2; Vogtle Electric Generating Plant, Units 1 and 2; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 -
Issuance of Amendments Regarding the Adoption of TSTF-65-A, Revision 1, "Use Of Generic Titles For Utility Positions" (TAC Nos. MF7466, MF7467, MF7468, MF7469, MF7470, And MF7471), January 13,2017
: 2. Edwin I. Hatch Nuclear Plant, Unit Nos. 1 And 2, Issuance of Amendments Regarding Revised Shutdown Margin (TAC Nos. MF3627 AND MF3628),
January 6, 2015
: 3. Proposed Guidance for Correction of Technical Specification Typographical Errors, SECY-96-238, dated November 19, 1996 Ladies and Gentlemen:
This letter requests Nuclear Regulatory Commission (NRC) approval of a correction of a typographical error in the Hatch Nuclear Plant (HNP) Unit 2 Technical Specifications (TS).
This error was inadvertently introduced during the processing of Unit 2 License Amendment 227 (Reference 1), and removed a TS change approved in License Amendment 217 (Reference 2}.
This was neither addressed in the notice to the public nor reviewed by the NRC, and thus falls within the scope of the guidance provided by SECY-96-238 (Reference 3). describes the typographical error and corrections. Enclosure 2 provides the Amendment 227 page as-issued, with the requested corrections noted. Enclosure 3 contains the corrected Amendment 227 page.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.
Respectfully submitted, J.J. Hutto Regulatory Affairs Director JJH/RMJ

U. S. Nuclear Regulatory Commission NL-17-0841 Page 2

==Enclosures:==
: 1. Description of Technical Specification Typographical Errors
: 2. Marked-up Technical Specification Page
: 3. Revised Technical Specification Page Cc:   Regional Administrator, Region II NRR Project Manager- Hatch Nuclear Plant Senior Resident Inspector- Hatch Nuclear Plant RTYPE: CHA02.004

Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Enclosure 1 Description of Technical Specification Typographical Errors to NL-17-0841 Description of Technical Specification Typographical Errors
: 1. Requested Action Consistent with the information contained in SECY-96-238, Southern Nuclear Operating Company (SNC) is requesting corrections of a typographical error that was inadvertently introduced into the Hatch Nuclear Plant (HNP) Unit 2 Technical Specification (TS). The error was introduced by the SNC staff in development of revised pages provided to the Nuclear Regulatory Commission (NRC) for issuance of Amendment 227. The pages provided did not incorporate a TS change previously approved by the NRC with the issuance of Amendment 217.
: 2. Typographical Error The Unit 2 definition of "Shutdown Margin" on page 1.1-5 was changed in Amendment 217 to state the following (with underline added to show additions):
SHUTDOWN              SDM shall be the amount of reactivity by which the reactor is subcritical MARGIN (SDM)          or would be subcritical throughout the operating cycle assuming that:
: a. The reactor is xenon free;
: b. The moderator temperature is~ 68&deg;F. corresponding to the most reactive state; and
: c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
When this page was issued in Amendment 227, however, the revised definition was not incorporated.
: 3. Correction to Affected Pages SECY-96-238 (Reference 3) provides guidance to correct inadvertent typographical errors in the Technical Specifications. This error described above was neither posted in the public notices nor was it reviewed by NRC as part of the license amendment process. Therefore, it may be corrected without a license amendment.
E1-1

Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Enclosure 2 Marked-up Technical Specification Page

Definitions 1.1 1.1  Definitions (continued)
PHYSICS TESTS          PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
: a.      Described in Chapter 14, Initial Tests and Operation, of the FSAR;
: b.      Authorized under the provisions of 10 CFR 50.59; or
: c.      Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND          The PTLR is the unit specific document that provides the reactor vessel TEMPERATURE           pressure and temperature limits, including heatup and cooldown rates, for LIMITS REPORT         the current reactor vessel fluence period. These pressure and (PTLR)           temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
RATED THERMAL POWER (RTP)           coolant of 2804 MWt.
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE TIME SHUTDOWN              SDM shall be the am l t of reactivity by which the reactor is subcritical MARGIN (SDM)          or would be subcritical assuming that:
                                                                          , corresponding to the
                                                             ~
: a.      The reactor is xenon free ;                 most reactive state
: b.      The moderator temperature      1  68&deg;F, and
: c.      All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn .
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED             A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS            systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency , so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER         THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
HATCH UNIT 2                                   1.1-5                            Amendment No. 227

Edwin I. Hatch Nuclear Plant, Unit 2 Correction of Technical Specification Typographical Error Enclosure 3 Revised Technical Specification Page

Definitions 1.1 1.1  Definitions (continued)
PHYSICS TESTS          PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
: a.       Described in Chapter 14, Initial Tests and Operation, of the FSAR;
: b.       Authorized under the provisions of 10 CFR 50.59; or
: c.       Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND          The PTLR is the unit specific document that provides the reactor vessel TEMPERATURE            pressure and temperature limits, including heatup and cooldown rates, for LIMITS REPORT         the current reactor vessel fluence period. These pressure and (PTLR)           temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.
RATED THERMAL          RTP shall be a total reactor core heat transfer rate to the reactor POWER (RTP)           coolant of 2804 MWt.
REACTOR               The RPS RESPONSE TIME shall be that time interval from when the PROTECTION             monitored parameter exceeds its RPS trip setpoint at the channel SYSTEM (RPS)           sensor until de-energization of the scram pilot valve solenoids. The RESPONSE TIME          response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SHUTDOWN               SDM shall be the amount of reactivity by which the reactor is subcritical MARGIN (SDM)           or would be subcritical throughout the operating cycle assuming that:
: a.      The reactor is xenon free;
: b.      The moderator temperature is ;:: 68&deg;F, corresponding to the most reactive state; and
: c.      All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
STAGGERED              A STAGGERED TEST BASIS shall consist of the testing of one of the TEST BASIS             systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency , so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER          THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
HATCH UNIT2                                     1.1-5                            Amendment No. 227}}