NL-16-2013, Transmittal of Revised Technical Specification Pages

Transmittal of Revised Technical Specification Pages

ML16300A429
Person / Time
Site:	Hatch
Issue date:	10/26/2016
From:	Pierce C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-16-2013
Download: ML16300A429 (12)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242

~ Southern Nuclear Tel 205.992.7872 Fax 205.992.7601 OCT 2 6 2016 Docket Nos.: 50-321 NL-16-2013 50-366 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant- Units 1 & 2 Transmittal of Revised Technical Specification Pages Ladies and Gentlemen:

By letter dated March 14, 2016, and as supplemented by letter dated May 17, 2016, Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to adopt TSTF-65-A, Rev. 1. SNC would like to amend this request to include three administrative corrections to the Edwin I. Hatch Nuclear Plant (HNP) Technical Specifications (TSs).

1. Include a missing "(Continued)" at the bottom of Unit 1 page 3.4-20 to signify that the Surveillance Requirements forTS 3.4.9 continue onto the following page.

2. Add the term STAGGERED TEST BASIS back to the Unit 2 Definitions. This term was added to page 1.1-5 of the definitions section in Unit 2 Amendment No.

220. Due to an unrelated change to this same page, this term was inadvertently deleted with the issuance of Amendment 221.

3. Update Unit 1 and Unit 2 Surveillance Requirement (SR) 3.6.4.1.3 to incorporate approved changes in Unit 1 Amendments 280 and 279 and in Unit 2 Amendments 224 and 223. By letter dated September 29, 2016, the Nuclear Regulatory Commission (NRC) issued HNP Amendments 279 (Unit 1) and 223 (Unit 2). By letter dated September 30, 2016, the NRC issued HNP Amendments 280 (Unit 1) and 224 (Unit 2). These Unit 1 and Unit 2 Amendments both made unrelated changes to SR 3.6.4.1.3. The changes approved in Amendments 279 (Unit 1) and 223 (Unit 2), however, were not incorporated in the TS pages issued in Amendments 280 (Unit 1) and 224 (Unit 2).

All of these administrative corrections simply incorporate changes to the TS that the NRC has previously approved. There is no proposed expansion of scope from what was previously approved by the NRC. As such, the conclusion of the No Significant Hazards Consideration (NSHC) provided in the March 14, 2016 LAR stating that a finding of "no significant hazards consideration" is justified remains unchanged.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

U.S. Nuclear Regulatory Commission NL-16-2013 Page2 Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.

C. R. Pierce Regulatory Affairs Director CRP/RMJ dbefore me this~ day of tfJJo ~ '2016.

~

My commission expires: iD_. i -de 11

Enclosures:

1. Marked-up Technical Specification Pages

2. Clean Typed Technical Specification Pages cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President- Engineering Mr. G. L. Johnson, Regulatory Affairs Manager- Hatch RType: CHA02.004 U. S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. M. D. Orenak, NRR Project Manager- Hatch Mr. D. H. Hardage, Senior Resident Inspector- Hatch State of Georgia Mr. J. H. Turner, Director- Environmental Protection Division

Edwin I. Hatch Nuclear Plant - Units 1 & 2 Transmittal of Revised Technical Specification Pages Enclosure 1 Marked-up Technical Specification Pages

RCS PIT Limits 3.4.9 SURVEILLANCE REQUIREMENTS _(continued)

SURVEILLANCE FREQUENCY SR 3.4.9.4 ------------------------------N0 TE-----------------------------

Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.

Verify the difference between the reactor coolant Once within temperature in the recirculation loop to be started 15 minutes prior to and the RPV coolant temperature iss 50°F. starting an idle recirculation pump SR 3.4.9.5 -----------------------------N 0 TE--------------------------

Only required to be met when tensioning/

detensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange Once within temperatures are within the limits specified in the 30 minutes prior to PTLR. tensioning/

detensioning the reactor vessel head bolting studs and in accordance with the Surveillance Frequency Control Program

!<continued)

HATCH UNIT 1 3.4-20 Amendment No . ~

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 assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°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.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

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 . pntinued)

HATCH UNIT 2 1.1-5 Amendment No.m

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed. the Surveillance Frequency Control Program SR 3.6.4.1.3 -----------------------------N0 TE-----------------------------

The number of standby gas treatment (SGT) subsystem(s) required for this Surveillance is dependent on the secondary containment configuration, and shall be one less than the number required to meet LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," for the given configuration.

~::i~-;:~~1~i!?~~~5EJ~:~~;~:~.~~;-------

Idowe t8d secondary containm:l~o ;:: 0 .20 inch In accordance with the Surveillance of vacuum water gauge in s 10 minut~. Frequency Control Program Jusing required standby gas l / .

---

~ ~~--------~----~--~--~

jtreatment (SGT) subsystem(s) . 1 (continued)

HATCH UNIT 1 3.6-35 Amendment No.m

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed. the Surveillance Frequency Control Program SR 3.6.4.1 .3 -----------------------------N0 TE -----------------------------

The number of standby gas treatment (SGT) subsystem(s) required for this Surveillance is dependent on the secondary containment configuration, and shall be one less than the number required to meet LCO 3.6.4.3, "Standby Gas Treatment (SGT} System," for the given configuration .

J ean be drawn down ~

In accordance with the Surveillance Frequency Control Program HATCH UNIT2 3.6-34 Amendment No . ~

Edwin I. Hatch Nuclear Plant - Units 1 & 2 Transmittal of Revised Technical Specification Pages Enclosure 2 Clean Typed Technical Specification Pages

RCS Pff Limits 3.4.9 SURVEILLANCE REQUIREMENTS icontinued)

SURVEILLANCE FREQUENCY SR 3.4.9.4 ------------------------------NOTE-----------------------------

Only required to be met in MODES 1, 2, 3, and 4 during startup of a recirculation pump.

Verify the difference between the reactor coolant Once within temperature in the recirculation loop to be started 15 minutes prior to and the RPV coolant temperature iss 50°F. starting an idle recirculation pump SR 3.4.9.5 ------------------------------NOTE-----------------------------

Only required to be met when tensioning/

detensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange Once within temperatures are within the limits specified in the 30 minutes prior to PTLR. tensioning/

detensioning the reactor vessel head bolting studs and in accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 1 3.4-20 Amendment No.

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 assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°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 UNIT2 1.1-5 Amendment No.

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SA 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed. the Surveillance Frequency Control Program SA 3.6.4.1.3 -----------------------------NOTE-----------------------------

The number of standby gas treatment (SGT) subsystem(s) required for this Surveillance is dependent on the secondary containment configuration, and shall be one less than the number required to meet LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," for the given configuration.

Verify secondary containment can be drawn In accordance with down to ;;:: 0.20 inch of vacuum water gauge in the Surveillance s 10 minutes using required standby gas Frequency Control treatment (SGT) subsystem(s). Program (continued)

HATCH UNIT 1 3.6-35 Amendment No.

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed. the Surveillance Frequency Control Program SR 3.6.4.1.3 -----------------------------NOTE-----------------------------

The number of standby gas treatment (SGT) subsystem(s) required for this Surveillance is dependent on the secondary containment configuration, and shall be one less than the number required to meet LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," for the given configuration.

Verify secondary containment can be drawn In accordance with down to t:: 0.20 inch of vacuum water gauge in the Surveillance s 10 minutes using required standby gas Frequency Control treatment (SGT) subsystems(s). Program (continued)

HATCH UNIT2 3.6-34 Amendment No.