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Text

Issuance of Amendments Regarding Multiple Technical Specification Changes (CAC Nos. MF5026 and MF5027)
	ML16231A041
Person / Time
Site:	Hatch
Issue date:	09/29/2016
From:	Michael Orenak; Plant Licensing Branch II
To:	Pierce C; Southern Nuclear Operating Co
	Orenak M, NRR/DORL/LPL2-1
References
	CAC MF5026, CAC MF5027
	Download: ML16231A041 (172)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Septanber '29, 2016 Mr. Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

P.O. Box 1295 I Bin 038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1AND2 - ISSUANCE OF AMENDMENTS REGARDING MULTIPLE TECHNICAL SPECIFICATION CHANGES (CAC NOS. MF5026 AND MF5027)

Dear Mr. Pierce:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment No. 279 to Renewed Facility Operating License No. DPR-57 and Amendment No. 223 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 10, 2014, as supplemented by letters dated May 4, 2015, October 15, 2015, and August 26, 2016.

The amendments revise Technical Specifications (TSs) by adopting 18 previously NRG-approved Technical Specifications Task Force (TSTF) travelers, two TSTF T-travelers, and one feature of the Improved Standard Technical Specifications (ISTS) not associated with a traveler. Southern Nuclear Operating Company, Inc. (SNC) stated that these changes would increase the consistency between the HNP TSs, the ISTS for Boiling Water Reactor/4 plants (NUREG-1433), and the TSs of the other plants in the SNC fleet.

C.R. Pierce A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 279 to DPR-57

2. Amendment No. 223 to NPF-5

3. Safety Evaluation cc w/enclosures: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 279 Renewed License No. DPR-57

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself; Georgia Power Company; Oglethorpe Power Corporation; Municipal Electric Authority of Georgia; and City of Dalton, Georgia (the owners), dated October 10, 2014, as supplemented by letters dated May 4, 2015, October 15, 2015, and August 26, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 Enclosure 1

E. The issuance of this amendment is in accordance with 1O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-57 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 279, are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~~~

Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed DPR-57 and Technical Specifications Date of Issuance: Septanber '29, 2016

ATTACHMENT TO LICENSE AMENDMENT NO. 279 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A, Technical Specifications (TSs),

with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4 4 TSs TSs 1.3-2 1.3-2 1.3-6 1.3-6 1.3-7 1.3-7 1.4-1 1.4-1 1.4-2 1.4-2 1.4-3 1.4-3 1.4-5 1.4-5 1.4-6 1.4-7 3.1-10 3.1-10 3.1-17 3.1-17 3.3-4 3.3-4 3.3-5 3.3-5 3.3-7 3.3-7 3.3-16 3.3-16 3.3-25 3.3-25 3.3-48 3.3-48 3.3-49 3.3-49 3.3-50 3.3-50 3.3-51 3.3-51 3.3-52 3.3-52 3.3-53 3.3-53 3.3-54 3.3-54 3.3-55 3.3-55a 3.3-55b 3.5-1 3.5-1 3.5-2 3.5-2 3.6-8 3.6-8 3.6-9 3.6-9 3.6-11 3.6-11

3.6-22 3.6-22 3.6-23 3.6-23 3.6-35 3.6-35 3.6-36 3.6-36 3.6-37 3.6-37 3.6-38 3.6-38 3.6-39 3.6-39 3.6-40 3.6-40 3.8-2 3.8-2 3.8-4 3.8-4 3.8-10 3.8-10 3.8-11 3.8-11 3.8-12 3.8-12 3.8-13 3.8-13 3.8-14 3.8-14 3.8-15 3.8-15 3.8-16 3.8-16 3.8-17 3.8-17 3.8-18 3.8-18 3.8-29 3.8-29 3.8-30 3.8-30 3.8-37 3.8-37 5.0-9 5.0-9 5.0-10 5.0-10 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15

for sample analysis or instrumentation calibration, or associated with radioactive apparatus or components; (6) Southern Nuclear, 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 the operation of the facility.

(C) This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below:

(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady sate reactor core power levels not in excess of 2804 megawatts thermal.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Plan (Appendix B), as revised through Amendment No. 279 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:

SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.

(3) Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained in the updated Fire Hazards Analysis and Fire Protection Program for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes Renewed License No. DPR-57 Amendment No. 279

Completion Times 1.3 1.3 Completion Times DESCRIPTION a. Must exist concurrent with the first inoperability; and (continued)

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery ... "

(continued)

HATCH UNIT 1 1.3-2 Amendment No. 279

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore 7 days subsystem Function X inoperable. subsystem to OPERABLE status.

B. One Function Y B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function Y inoperable. subsystem to OPERABLE status.

C. One Function X C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function X inoperable. subsystem to OPERABLE AND status.

One Function Y OR subsystem inoperable. C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to OPERABLE status.

(continued)

HATCH UNIT 1 1.3-6 Amendment No. 279

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions Band C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

(continued)

HATCH UNIT 1 1.3-7 Amendment No. 279

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Conditions for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria. Some surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

(continued)

HATCH UNIT 1 1.4-1 Amendment No. 279

Frequency 1.4 1.4 Frequency DESCRIPTION a. The Surveillance is not required to be met in the MODE or other (continued) specified condition to be entered; or

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or

c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then SR 3.0.3 becomes applicable.

(continued)

HATCH UNIT 1 1.4-2 Amendment No. 279

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the mode or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

<:: 25% RTP 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to<::: 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

(continued)

HATCH UNIT 1 1.4-3 Amendment No. 279

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

N()TE---------------------------

()n ly required to be met in M()DE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in M()DE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by SR 3.0.2) interval, but the unit was not in M()DE 1, there would be no failure of the SR nor failure to meet the LC(). Therefore, no violation of SR 3.0.4 occurs when changing M()DES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the M()DE change was not made into M()DE 1. Prior to entering M()DE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

N()TE---------------------------

()nly required to be performed in M()DE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in M()DE 1, 2, or 3 (the assigned Applicability of the associated LC()) between performances.

(continued)

HATCH UNIT 1 1.4-5 Amendment No. 279

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE---------------------------

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no (continued)

HATCH UNIT 1 1.4-6 Amendment No. 279

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-6 (continued) violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

HATCH UNIT 1 1.4-7 Amendment No. 279

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

N 0 TE------------------------------------------------------------

0 uring single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the Prior to exceeding limits of Table 3.1.4-1 with reactor steam dome 40% RTP after each pressure<::: 800 psig. reactor shutdown

<:: 120 days SR 3.1.4.2 Verify, for a representative sample, each tested In accordance with control rod scram time is within the limits of the Surveillance Table 3.1.4-1 with reactor steam dome pressure Frequency Control

<::: 800 psig. Program SR 3.1.4.3 Verify each affected control rod scram time is Prior to declaring within the limits of Table 3.1.4-1 with any reactor control rod steam dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding within the limits of Table 3.1.4-1 with reactor 40% RTP after fuel steam dome pressure<::: 800 psig. movement within the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time HATCH UNIT 1 3.1-10 Amendment No. 279

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Sodium pentaborate A.1 Restore sodium 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months solution not within pentaborate solution to Region A limits of within Region A limits.

Figure 3.1.7-1 or 3.1.7-2, but within the Region B limits.

B. One SLC subsystem B.1 Restore SLC 7 days inoperable for reasons subsystem to other than Condition A. OPERABLE status.

C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to other than Condition A. OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

HATCH UNIT 1 3.1-17 Amendment No. 279

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.2 ------------------------------N 0 TE----------------------------

N ot required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 24% RTP.

Verify the absolute difference between the In accordance with average power range monitor (APRM) channels the Surveillance and the calculated power is s 2% RTP while Frequency Control operating at~ 24% RTP. Program SR 3.3.1.1.3 (Not used.)

SR 3.3.1.1.4 ----------------------------N 0 TE------------------------------

N ot required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 (Not used.)

(continued)

HATCH UNIT 1 3.3-4 Amendment No. 279

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7 (Not used.)

SR 3.3.1.1.8 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 ----------------------------NOTE------------------------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 Verify Turbine Stop Valve - Closure and In accordance with Turbine Control Valve Fast Closure, Trip Oil the Surveillance Pressure - Low Functions are not bypassed Frequency Control when THERMAL POWER is~ 27.6% RTP. Program SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (cont1 n ued)

HATCH UNIT 1 3.3-5 Amendment No. 279

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1(page1 of3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitor

a. Neutron Flux - High 2 2(d) G SR 3.3.1.1.1 ::; 120/125 SR 3.3.1.1.4 divisions of full SR 3.3.1.1.13 scale SR 3.3.1.1.15 5(a) 2(d) H SR 3.3.1.1.1 ::; 120/125 SR 3.3.1.1.5 divisions of full SR 3.3.1.1.13 scale SR 3.3.1.1.15

b. lnop 2 2(d) G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) 2(d) H SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power Range Monitor

a. Neutron Flux - High 2 3(c) G SR 3.3.1.1.1 => 20% RTP (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13

b. Simulated Thermal 3(c) F SR 3.3.1.1.1 => 0.57W+

Power- High SR 3.3.1.1.2 56.8% RTP SR 3.3.1.1.8 and SR 3.3.1.1.10 :>115.5%

SR 3.3.1.1.13 RTP(b)

c. Neutron Flux - High 3(c) F SR 3.3.1.1.1 s 120% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13

d. lnop 1, 2 3(c) G SR 3.3.1.1.10 NA continued (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.57W + 56.8% - 0.57 tiW RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

(c) Each APRM channel provides inputs to both trip systems.

(d) One channel in each quadrant of the core must be OPERABLE whenever the IRMs are required to be OPERABLE. Both the RWM and a second licensed operator must verify compliance with the withdrawal sequence when less than three channels in any trip system are OPERABLE.

HATCH UNIT 1 3.3-7 Amendment No. 279

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.2 Verify by administrative Immediately methods that startup with RWM inoperable has not been performed in the last 12 months.

AND C.2.2 Verify movement of During control rod control rods is in movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control rod reactor shutdown. control rods is in movement compliance with BPWS by a second licensed operator or other qualified member of the technical staff.

E. One or more Reactor Mode E.1 Suspend control rod Immediately Switch - Shutdown Position withdrawal.

channels inoperable.

AND E.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

HATCH UNIT 1 3.3-16 Amendment No. 279

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1(page1of1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Steam Dome Pressure 2 E

2. Reactor Vessel Water Level

a. -317 inches to -17 inches 2 E

b. -150 inches to +60 inches 2 E

c. 0 inches to +60 inches 2 E

d. 0 inches to +400 inches 1 NA

3. Suppression Pool Water Level

a. 0 inches to 300 inches 2 E

b. 133 inches to 163 inches 2 E

4. Drywell Pressure

a. -1 O psig to +90 psig 2 E

b. -5 psig to +5 psig 2 E C. 0 psig to +250 psig 2 E

5. Drywell Area Radiation (High Range) 2 F

6. Penetration Flow Path Primary Containment Isolation 2 per penetration flow E Valve Position path (a)(b)

7. (Deleted)

8. (Deleted) 2(C) E

9. Suppression Pool Water Temperature 6 E

10. Drywell Temperature in Vicinity of Reactor Level Instrument Reference Leg

11. Diesel Generator (DG) Parameters 1 per DG NA

a. Output Voltage 1 per DG NA

b. Output Current 1 per DG NA

c. Output Power 1 per DG NA

d. Battery Voltage 2 E

12. RHR Service Water Flow (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) Monitoring each of four quadrants.

HATCH UNIT 1 3.3-25 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

N 0 TES-----------------------------------------------------------

1. Penetration flow paths except for 18 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. Functions 2.a, 2.b, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.b, 6.b, 7.a, and 7.b B. ---------------N 0 TE------------- B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Not applicable for capability.

Function 5.c.

One or more automatic Functions with isolation capability not maintained.

C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or B Table 3.3.6.1-1 for the not met. channel.

(continued)

HATCH UNIT 1 3.3-48 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Isolate associated main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced steam line (MSL).

in Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by Required E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced penetration flow in Table 3.3.6.1-1. path(s).

G. As required by Required G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action C.1 and referenced penetration flow in Table 3.3.6.1-1. path(s).

H. As required by Required H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced in Table 3.3.6.1-1. AND OR H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and associated Completion Time of Condition F or G not met.

(continued)

HATCH UNIT 1 3.3-49 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required 1.1 Declare Standby Liquid 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced Control (SLC) System in Table 3.3.6.1-1. inoperable.

OR 1.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup (RWCU) System.

J. As required by Required J.1 Initiate action to restore Immediately Action C.1 and referenced channel to OPERABLE in Table 3.3.6.1-1. status.

OR J.2 Initiate action to isolate Immediately the Residual Heat Removal (RHR)

Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS

N 0 TES-----------------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 1 3.3-50 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program HATCH UNIT 1 3.3-51 Amendment No. 279 I

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water Level - 1,2,3 2 D SR 3.3.6.1.1 <: -113 inches Low Low Low, Level 1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Main Steam Line Pressure - 2 E SR 3.3.6.1.3 <= 825 psig Low SR 3.3.6.1.6

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 ::; 138% rated Flow- High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

d. Condenser Vacuum - Low 1, 2 D SR 3.3.6.1.3 <: 7 inches Hg 2(a), 3(a) SR 3.3.6.1.6 vacuum

e. Main Steam Tunnel 1,2,3 6 D SR 3.3.6.1.1 :5194°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

f. Turbine Building Area 1,2,3 16(b) D SR 3.3.6.1.2 ::; 200°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

2. Primary Containment Isolation

a. Reactor Vessel Water Level 1,2,3 2 H SR 3.3.6.1.1 <: 0 inches

- Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Drywell Pressure - High 1,2,3 2 H SR 3.3.6.1.1 ::; 1.92 psig I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 continued (a) With any turbine stop valve not closed.

(b) With 8 channels per trip string. Each trip string shall have 2 channels per main steam line, with no more than 40 ft separating any two OPERABLE channels.

HATCH UNIT 1 3.3-52 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 Table3.3.6.1-1 (page2of5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

2. Primary Containment Isolation (continued)

C. Drywell Radiation - 1,2,3 F SR 3.3.6.1.1 s 138 R/hr High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

d. Reactor Building Exhaust 1,2,3 2 H SR 3.3.6.1.1 s 80 mR/hr I Radiation - High SR 3.3.6.1.3 SR 3.3.6.1.6

e. Refueling Floor Exhaust 1,2,3 2 H SR 3.3.6.1.1 s 80 mR/hr I Radiation - High SR 3.3.6.1.3 SR 3.3.6.1.6

3. High Pressure Coolant Injection (HPCI) System Isolation

a. HPCI Steam Line Flow - 1,2,3 F SR 3.3.6.1.1 s 303% rated High SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

b. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 <! 100 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

c. HPCI Turbine Exhaust 1,2,3 2 F SR 3.3.6.1.1 s 20 psig Diaphragm Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

d. Drywell Pressure - High 1,2,3 F SR 3.3.6.1.1 s 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

e. HPCI Pipe Penetration Roorr 1,2,3 F SR 3.3.6.1.1 s 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

f. Suppression Pool Area 1,2,3 F SR 3.3.6.1.1 s 169°F Ambient Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 continued HATCH UNIT 1 3.3-53 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

3. HPCI System Isolation (continued)

g. Suppression Pool Area 1,2,3 F SR 3.3.6.1.4 :;; 16 minutes Temperature - Time Delay SR 3.3.6.1.6 15 seconds Relays

h. Suppression Pool Area 1,2,3 F SR 3.3.6.1.1 :;; 42°F Differential Temperature - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

i. Emergency Area Cooler 1,2,3 F SR 3.3.6.1.1 :;; 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line Flow - 1,2,3 F SR 3.3.6.1.1 :;; 306% rated High SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

b. RCIC Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 2! 60 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 C. RCIC Turbine Exhaust 1,2,3 2 F SR 3.3.6.1.1 :;; 20 psig Diaphragm Pressure - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

d. Drywell Pressure - High 1,2,3 F SR 3.3.6.1.1 :;; 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

e. RCIC Suppression Pool 1,2,3 F SR 3.3.6.1.1 :;; 169°F Ambient Area SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

f. Suppression Pool Area 1,2,3 F SR 3.3.6.1.4 :;; 31 minutes Temperature - Time Delay SR 3.3.6.1.6 15 seconds Relays continued HATCH UNIT 1 3.3-54 Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

4. RCIC System Isolation (continued)

g. RCIC Suppression Pool 1,2,3 F SR 3.3.6.1.1 :S 42°F Area Differential SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

h. Emergency Area Cooler 1,2,3 F SR 3.3.6.1.1 :S 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

5. RWCU System Isolation

a. Area Temperature - High 1,2,3 1 per area F SR 3.3.6.1.1 :S 150°F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Area Ventilation 1,2,3 1 per area F SR 3.3.6.1.1 :S 67°F Differential Temperature - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

c. SLC System Initiation 1,2 1(C) SR 3.3.6.1.6 NA

d. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 <: -47 inches Level - Low Low, Level 2 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

6. RHR Shutdown Cooling System Isolation

a. Reactor Steam Dome 1,2,3 F SR 3.3.6.1.1 :S 145 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3,4,5 2 (d) J SR 3.3.6.1.1 <: 0 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 (continued)

(c) SLC System Initiation only inputs into one of the two trip systems.

(d) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

HATCH UNIT 1 3.3-55a Amendment No. 279

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

7. Traversing lncore Probe System Isolation

a. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 2! 0 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Drywell Pressure - High 1,2,3 2 G SR 3.3.6.1.1 s 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 HATCH UNIT 1 3.3-55b Amendment No. 279

ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure s 150 psig.

ACTIONS

N 0 TE-------------------------------------------------------------

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray subsystem ECCS injection/spray inoperable. subsystem(s) to OPERABLE status.

OR One LPCI pump in both LPCI subsystems inoperable.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 1 3.5-1 Amendment No. 279

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System inoperable. C.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means RCIC System is OPERABLE.

AND C.2 Restore HPCI System 14 days to OPERABLE status.

D. HPCI System inoperable. D.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

AND OR Condition A entered.

D.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem to OPERABLE status.

E. Two or more ADS valves E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND OR E.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and dome pressure to associated Completion =:;; 150 psig.

Time of Condition C or D not met.

F. Two or more low pressure F.1 Enter LCO 3.0.3. Immediately ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and two or more ADS valves inoperable.

HATCH UNIT 1 3.5-2 Amendment No. 279

PC IVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------------N 0 TES-----------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment B. -------------N 0 TE--------------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one two PCIVs. closed and de-activated

automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two PCIVs inoperable except due to leakage not within limit.

(continued)

HATCH UNIT 1 3.6-8 Amendment No. 279

PC IVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------------N 0 TE------------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by excess flow check penetration flow paths with use of at least one valve (EFCV) line and only one PCIV. closed and de-activated penetrations with a

automatic valve, closed closed system manual valve, or blind One or more penetration flange. AND flow paths with one PCIV inoperable except due to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for leakage not within limits. AND EFCV line and penetrations with a C.2 -----------NOTES---------- closed system

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more penetration D.1 Restore leakage to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow paths with leakage not within limit.

within limit.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 1 3.6-9 Amendment No. 279

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.2 ------------------------------N 0 TES---------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside the Surveillance primary containment and not locked, sealed, or Frequency Control otherwise secured and is required to be closed Program during accident conditions is closed.

SR 3.6.1.3.3 -----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside MODE 2 or 3 from primary containment and not locked, sealed, or MODE 4 if primary otherwise secured and is required to be closed containment was during accident conditions is closed. de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe In accordance with (Tl P) shear isolation valve explosive charge. the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, In accordance with automatic PCIV, except for MSIVs, is within limits. the lnservice Testing Program (continued)

HATCH UNIT 1 3.6-11 Amendment No. 279

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion POWER until all Time of Condition A not OPERABLE IRM met. channels s 25/40 divisions of full scale on Range 7.

C. Suppression pool average C.1 Suspend all testing that Immediately temperature> 105°F. adds heat to the suppression pool.

AND Any OPERABLE IRM channel > 25/40 divisions of full scale on Range 7.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool average D.1 Place the reactor mode Immediately temperature> 110°F. switch in the shutdown position.

AND D.2 Determine suppression Once per 30 minutes pool average temperature.

AND D.3 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 1 3.6-22 Amendment No. 279

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool average E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperature > 120°F. reactor vessel to

< 200 psig.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance with within the applicable limits. the Surveillance Frequency Control Program 5 minutes when performing testing that adds heat to the suppression pool HATCH UNIT 1 3.6-23 Amendment No. 279

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 ~ 0.20 inch of vacuum water gauge in the Surveillance s 120 seconds using required standby gas Frequency Control treatment (SGT) subsystem(s). Program (continued)

HATCH UNIT 1 3.6-35 Amendment No. 279

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.4.1.4 -----------------------------N 0 TE------------------------------

Th e number of 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 the secondary containment can be In accordance with maintained ;;:: 0.20 inch of vacuum water gauge the Surveillance for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using required SGT subsystem(s) at Frequency Control a flow rate~ 4000 cfm per subsystem. Program HATCH UNIT 1 3.6-36 Amendment No. 279

SCI Vs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES-------------------------------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow paths with one SCIV penetration flow path by inoperable. use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange.

AND A.2 -----------NOTES-----------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

(continued)

HATCH UNIT 1 3.6-37 Amendment No. 279

SCI Vs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B. One or more penetration B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow paths with two SCIVs penetration flow path by inoperable. use of at least one closed and deactivated automatic valve, closed manual valve, or blind flange.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.

C.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and D.1 -------------N 0 TE-----------

associated Completion LCO 3.0.3 is not Time of Condition A or B applicable.

not met during movement --------------------------------

of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS, or during secondary containment.

OPDRVs.

(continued)

HATCH UNIT 1 3.6-38 Amendment No. 279

SCI Vs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) AND D.2 Suspend CORE Immediately ALTERATIONS.

D.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation In accordance with manual valve and blind flange that is not locked, the Surveillance sealed, or otherwise secured and is required to be Frequency Control closed during accident conditions is closed. Program SR 3.6.4.2.2 Verify the isolation time of each power operated, In accordance with automatic SCIV is within limits. the Surveillance Frequency Control Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to the In accordance with isolation position on an actual or simulated the Surveillance actuation signal. Frequency Control Program HATCH UNIT 1 3.6-39 Amendment No. 279

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 The Unit 1 and Unit 2 SGT subsystems required to support LCO 3.6.4.1, "Secondary Containment," shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE AL TERA TIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required Unit 1 SGT A.1 Restore required Unit 1 30 days from subsystem inoperable SGT subsystem to discovery of failure to while: OPERABLE status. meet the LCO

1. Four SGT subsystems required OPERABLE, and

2. Unit 1 reactor building-to-refueling floor plug not installed.

B. One required Unit 2 SGT B.1 Restore required SGT 7 days subsystem inoperable. subsystem to OPERABLE status.

OR One required Unit 1 SGT subsystem inoperable for reasons other than Condition A.

(continued)

HATCH UNIT 1 3.6-40 Amendment No. 279

AC Sources - Operating 3.8.1 ACTIONS

N 0 TE-------------------------------------------------------------

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuits. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery feature(s) with no offsite of no offsite power to power available one 4160 V ESF bus inoperable when the concurrent with redundant required inoperability of feature(s) are redundant required inoperable. feature(s)

AND A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status.

B. One Unit 1 or the swing B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG inoperable. OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

HATCH UNIT 1 3.8-2 Amendment No. 279

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 (continued) AND 14 days for the swing diesel with maintenance restrictions met C. One required Unit 2 DG C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable OPERABLE required offsite circuit( s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery feature(s), supported by of Condition C the inoperable DG, concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are inoperable. feature(s)

AND C.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR C.3.2 Perform SR 3.8.1.2.a for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

(continued)

HATCH UNIT 1 3.8-4 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 -----------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1 or 2. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of unit power In accordance with supply from the normal offsite circuit to the the Surveillance alternate offsite circuit. Frequency Control Program SR 3.8.1.7 ----------------------------N0 TES-----------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2, except for the swing DG. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. For the swing DG, this Surveillance shall not be performed in MODE 1 or 2 using the Unit 1 controls.

Credit may be taken for unplanned events that satisfy this SR.

2. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG rejects a load greater than or In accordance with equal to its associated single largest post-accident the Surveillance load, and: Frequency Control Program

a. Following load rejection, the frequency is s 65.5 Hz; and

b. Within 3 seconds following load rejection, the voltage is~ 3740 V ands 4580 V.

(continued)

HATCH UNIT 1 3.8-10 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.8 ---------------------------NOTES------------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2, except for the swing DG. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. For the swing DG, this Surveillance shall not be performed in MODE 1 or 2 using the Unit 1 controls.

Credit may be taken for unplanned events that satisfy this SR.

2. If grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

3. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factor s 0.88 In accordance with does not trip and voltage is maintained s 4800 V the Surveillance during and following a load rejection of<:: 2775 kW. Frequency Control Program (continued)

HATCH UNIT 1 3.8-11 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.9 ----------------------------N 0 TES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite In accordance with power signal: the Surveillance Frequency Control

a. De-energization of emergency buses; Program

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in :s; 12 seconds,

2. Energizes auto-connected shutdown loads through automatic load sequence timing devices,

3. Maintains steady state voltage

~ 3740 V and :s; 4243 V,

4. Maintains steady state frequency

~ 58.8 Hz and :s; 61.2 Hz, and

5. Supplies permanently connected and auto-connected shutdown loads for ~ 5 minutes.

(continued)

HATCH UNIT 1 3.8-12 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.10 ----------------------------N 0 TES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core In accordance with Cooling System (ECCS) initiation signal each DG the Surveillance auto-starts from standby condition and: Frequency Control Program

a. Ins 12 seconds after auto-start achieves voltage~ 3740 V, and after steady state conditions are reached, maintains voltage

~ 3740 V ands 4243 V;

b. In s 12 seconds after auto-start achieves frequency~ 58.8 Hz, and after steady state conditions are reached, maintains frequency~ 58.8 Hz and s 61.2 Hz; and

c. Operates for ~ 5 minutes.

(continued)

HATCH UNIT 1 3.8-13 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.11 ---------------------------N 0 TE--------------------------------

T his Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

In accordance with Verify each DG's non-critical automatic trips are the Surveillance bypassed on actual or simulated loss of voltage Frequency Control signal on the emergency bus concurrent with an Program actual or simulated ECCS initiation signal.

(continued)

HATCH UNIT 1 3.8-14 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.12 ----------------------------N 0 TES-----------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2, unless the other two DGs are OPERABLE. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. If either of the other two DGs becomes inoperable, this surveillance shall be suspended.

Credit may be taken for unplanned events that satisfy this SR.

3. If grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

4. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factors 0.88 In accordance with operates for ~ 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: the Surveillance Frequency Control

a. For~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded ~ 3000 kW; and Program

b. For the remaining hours of the test loaded

~ 2775 kW and s 2825 kW.

(continued)

HATCH UNIT 1 3.8-15 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 -----------------------------N 0 TES----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded

~ 2565 kW. Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in In accordance with s 12 seconds, voltage~ 3740 V and frequency the Surveillance

~ 58.8 Hz; and after steady state conditions are Frequency Control reached, maintains voltage~ 3740 V ands 4243 V Program and frequency~ 58.8 Hz and s 61.2 Hz.

SR 3.8.1.14 ----------------------------N 0 TE-------------------------------

T his Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY providec an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG: In accordance with the Surveillance

a. Synchronizes with offsite power source Frequency Control while loaded with emergency loads upon a Program simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

(continued)

HATCH UNIT 1 3.8-16 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 ----------------------------N 0 TE-------------------------------

T his Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

In accordance with Verify with a DG operating in test mode and the Surveillance connected to its bus, an actual or simulated ECCS Frequency Control initiation signal overrides the test mode by: Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.16 -----------------------------N 0 TE------------------------------

Th is Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load In accordance with block is within +/- 10% of design interval for each the Surveillance load sequence timing device. Frequency Control Program (continued)

HATCH UNIT 1 3.8-17 Amendment No. 279

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.17 -----------------------------N 0 TES----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated ECCS initiation signal: Frequency Control Program

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in s 12 seconds,

2. Energizes auto-connected emergency loads through automatic load sequence timing devices,

3. Achieves steady state voltage

~ 3740 V ands 4243 V,

4. Achieves steady state frequency

~ 58.8 Hz and s 61.2 Hz, and

5. Supplies permanently connected and auto-connected emergency loads for~ 5 minutes.

(continued)

HATCH UNIT 1 3.8-18 Amendment No. 279

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.6 Verify each required battery charger supplies In accordance with

400 amps for station service subsystems, and the Surveillance

100 amps for DG subsystems at ;

: 129 V for Frequency Control

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Program SR 3.8.4.7 -----------------------------N 0 TES----------------------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3, except for the swing DG battery. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads for the design duty cycle when Frequency Control subjected to a battery service test. Program (continued)

HATCH UNIT 1 3.8-29 Amendment No. 279

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.8 -----------------------------N 0 TE------------------------------

T his Surveillance shall not normally be performed in MODE 1, 2, or 3, except for the swing DG battery. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is~ 80% of the In accordance with manufacturer's rating when subjected to a the Surveillance performance discharge test or a modified Frequency Control performance discharge test. Program 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating 24 months when battery has reached 85% of expected life with capacity ~ 100% of manufacturer's rating SR 3.8.4.9 For required Unit 2 DC sources, the SRs of Unit 2 In accordance with Specification 3.8.4 are applicable. applicable SRs HATCH UNIT 1 3.8-30 Amendment No. 279

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more (Unit 1 or B.1 Restore DG DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months swing bus) DG DC electrical power electrical power distribution distribution subsystem subsystems inoperable. to OPERABLE status.

C. One or more (Unit 1 or C.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months swing bus) AC electrical power distribution power distribution subsystem to subsystems inoperable. OPERABLE status.

D. One Unit 1 station service D.1 Restore Unit 1 station 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power service DC electrical distribution subsystem power distribution inoperable. subsystem to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND or D not met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two or more electrical F.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

HATCH UNIT 1 3.8-37 Amendment No. 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 1O CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 1O CFR 50, Appendix I;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary as follows:

1) For noble gases, less than or equal to a dose rate of 500 mrem/year to the total body and less than or equal to a dose rate of 3000 mrem/year to the skin, and

2) For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, less than or equal to a dose rate of 1500 mrem/year to any organ;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

(continued)

HATCH UNIT 1 5.0-9 Amendment No. 279

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit This program provides controls to track FSAR Section 4.2, cyclic and transient occurrences, to ensure that reactor coolant pressure boundary components are maintained within the design limits.

5.5.6 lnservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports.

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing lnservice lnservice Testing Activities Testing Activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days

b. The provisions of SR 3.0.2 are applicable to the frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

5.5.7 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2, Sections C.5.c and C.5.d, and in accordance with Regulatory Guide 1.52, Revision 2.

(continued)

HATCH UNIT 1 5.0-10 Amendment No. 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

The program shall include:

a. The limits for the concentrations of hydrogen in the main condenser offgas treatment system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 1O CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within limits,

2. A flash point and kinematic viscosity within limits for ASTM 20 fuel oil, and

3. A water and sediment content within limits;

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a., above, are within limits for ASTM 20 fuel oil; and (continued)

HATCH UNIT 1 5.0-13 Amendment No. 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Diesel Fuel Oil Testing Program (continued)

c. Total particulate concentration of the fuel oil is ~ 10 mg/liter when tested every 92 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance frequencies.

5.5.10 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

(continued)

HATCH UNIT 1 5.0-14 Amendment No. 279

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Safety Function Determination Program (SFDP) (continued)

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRG approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRG approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of item b above shall be reviewed and approved by the NRG prior to implementation. Changes to the Bases implemented without prior NRG approval shall be provided to the NRG on a frequency consistent with 10 CFR 50.71(e).

(continued)

HATCH UNIT 1 5.0-15 Amendment No. 279

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 223 Renewed License No. NPF-5

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself; Georgia Power Company; Oglethorpe Power Corporation; Municipal Electric Authority of Georgia; and City of Dalton, Georgia (the owners), dated October 10, 2014, as supplemented by letters dated May 4, 2015, October 15, 2015, and August 26, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 Enclosure 2

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. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-5 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 223 are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed NPF-5 and Technical Specifications Date of Issuance: Septenber 29, Xl16

ATTACHMENT TO LICENSE AMENDMENT NO. 223 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A, Technical Specifications (TSs),

with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License 4 4 TSs TSs 1.3-2 1.3-2 1.3-6 1.3-6 1.3-7 1.3-7 1.4-1 1.4-1 1.4-2 1.4-2 1.4-3 1.4-3 1.4-5 1.4-5 1.4-6 1.4-7 3.1-10 3.1-10 3.1-17 3.1-17 3.3-4 3.3-4 3.3-5 3.3-5 3.3-7 3.3-7 3.3-16 3.3-16 3.3-25 3.3-25 3.3-48 3.3-48 3.3-49 3.3-49 3.3-50 3.3-50 3.3-51 3.3-51 3.3-52 3.3-52 3.3-53 3.3-53 3.3-54 3.3-54 3.3-55 3.3-55a 3.3-55b 3.5-1 3.5-1 3.5-2 3.5-2 3.6-8 3.6-8 3.6-9 3.6-9 3.6-11 3.6-11

3.6-22 3.6-22 3.6-23 3.6-23 3.6-34 3.6-34 3.6-35 3.6-35 3.6-36 3.6-36 3.6-37 3.6-37 3.6-38 3.6-38 3.6-40 3.6-40 3.8-2 3.8-2 3.8-4 3.8-4 3.8-10 3.8-10 3.8-11 3.8-11 3.8-12 3.8-12 3.8-13 3.8-13 3.8-14 3.8-14 3.8-15 3.8-15 3.8-16 3.8-16 3.8-17 3.8-17 3.8-18 3.8-18 3.8-29 3.8-29 3.8-30 3.8-30 3.8-38 3.8.38 5.0-9 5.0-9 5.0-10 5.0-10 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15

(6) Southern Nuclear, pursuant to the Act and 1O CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(C) This renewed license shall be deemed to contain, and is subject to, the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions 2 specified or incorporated below:

(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady sate reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B); as revised through Amendment No. 223 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.

(a) Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained 2

The original licensee authorized to possess, use, and operate the facility with Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

Renewed License No. NPF-5 Amendment No. 223

Completion Times 1.3 1.3 Completion Times DESCRIPTION a. Must exist concurrent with the first inoperability; and (continued)

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery ... "

(continued)

HATCH UNIT 2 1.3-2 Amendment No. 223

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore 7 days subsystem Function X inoperable. subsystem to OPERABLE status.

B. One Function Y B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function Y inoperable. subsystem to OPERABLE status.

C. One Function X C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function X inoperable. subsystem to OPERABLE AND status.

One Function Y OR subsystem inoperable. C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to OPERABLE status.

(continued)

HATCH UNIT 2 1.3-6 Amendment No. 223

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions Band Care exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

(continued)

HATCH UNIT 2 1.3-7 Amendment No. 223

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Conditions for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)

Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria. Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

(continued)

HATCH UNIT 2 1.4-1 Amendment No. 223

Frequency 1.4 1.4 Frequency DESCRIPTION a. The Surveillance is not required to be met in the MODE or other (continued) specified condition to be entered; or

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or

c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then SR 3.0.3 becomes applicable.

(continued)

HATCH UNIT 2 1.4-2 Amendment No. 223

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the mode or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

25% RTP 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to;:: 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

(continued)

HATCH UNIT 2 1.4-3 Amendment No. 223 I

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

N 0 TE-----------------------------

0 nly required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by SR 3.0.2) interval, but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

N 0 TE-----------------------------

0 n Iy required to be performed in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1, 2, or 3 (the assumed Applicability of the associated LCO) between performances.

(continued)

HATCH UNIT 2 1.4-5 Amendment No. 223

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1 .

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed, If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

N 0 TE-----------------------------

N ot required to be met in MODE 3.

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no (continued)

HATCH UNIT 2 1.4-6 Amendment No. 223

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-6 (continued) violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

HATCH UNIT 2 1.4-7 Amendment No. 223

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

N 0 TE------------------------------------------------------------

0 u ring single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the Prior to exceeding limits of Table 3.1.4-1 with reactor steam dome 40% RTP after each pressure~ 800 psig. reactor shutdown

~ 120 days SR 3.1.4.2 Verify, for a representative sample, each tested In accordance with control rod scram time is within the limits of the Surveillance Table 3.1.4-1 with reactor steam dome pressure Frequency Control

~ 800 psig. Program SR 3.1.4.3 Verify each affected control rod scram time is Prior to declaring within the limits of Table 3.1.4-1 with any reactor control rod steam dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding within the limits of Table 3.1.4-1 with reactor 40% RTP after fuel steam dome pressure~ 800 psig. movement within the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time HATCH UNIT 2 3.1-10 Amendment No. 223

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Sodium pentaborate A.1 Restore sodium 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months solution not within pentaborate solution to Region A limits of within Region A limits.

Figure 3.1.7-1or3.1.7-2, but within the Region B limits.

B. One SLC subsystem B.1 Restore SLC 7 days inoperable for reasons subsystem to other than Condition A. OPERABLE status.

C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to other than Condition A. OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

HATCH UNIT 2 3.1-17 Amendment No. 223

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.2 -----------------------------N 0 TE-----------------------------

N ot required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER;?: 24% RTP.

Verify the absolute difference between the In accordance with average power range monitor (APRM) channels the Surveillance and the calculated power is s 2% RTP while Frequency Control operating at;?: 24% RTP. Program SR 3.3.1.1.3 (Not used.)

SR 3.3.1.1.4 -----------------------------NOTE-----------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 (Not used.)

(continued)

HATCH UNIT 2 3.3-4 Amendment No. 223

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7 (Not used.)

SR 3.3.1.1.8 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 -----------------------------NOTE-----------------------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 Verify Turbine Stop Valve - Closure and In accordance with Turbine Control Valve Fast Closure, Trip Oil the Surveillance Pressure - Low Functions are not bypassed Frequency Control when THERMAL POWER is~ 27.6% RTP. Program SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 2 3.3-5 Amendment No. 223

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitor

a. Neutron Flux - High 2 2(d) G SR 3.3.1.1.1 $ 120/125 SR 3.3.1.1.4 divisions of full SR 3.3.1.1.13 scale SR 3.3.1.1.15 5(a) 2(d) H SR 3.3.1.1.1 $ 120/125 SR 3.3.1.1.5 divisions of full SR 3.3.1.1.13 scale SR 3.3.1.1.15

b. lnop 2 2(d) G SR 3.3.1.1.4 NA SR 3.3.1.1.15 5(a) 2(d) H SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power Range Monitor

a. Neutron Flux - High 2 3(c) G SR 3.3.1.1.1 :> 20% RTP (Setdown) SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13

b. Simulated Thermal 3(c) F SR 3.3.1.1.1 :> 0.57W+

Power- High SR 3.3.1.1.2 56.8% RTP SR 3.3.1.1.8 and:> 115.5%

SR 3.3.1.1.10 RTP(b)

SR 3.3.1.1.13

c. Neutron Flux - High 3(c) F SR 3.3.1.1.1 :> 120% RTP SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13

d. lnop 1, 2 3(c) G SR 3.3.1.1.10 NA continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.57W + 56.8% - 0.57 tiW RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

(c) Each APRM channel provides inputs to both trip systems.

(d) One channel in each quadrant of the core must be OPERABLE whenever the IRMs are required to be OPERABLE. Both the RWM and a second licensed operator must verify compliance with the withdrawal sequence when less than three channels in any trip system are OPERABLE.

HATCH UNIT 2 3.3-7 Amendment No. 223

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1.2 Verify by administrative Immediately methods that startup with RWM inoperable has not been performed in the last 12 months.

AND C.2.2 Verify movement of During control rod control rods is in movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of During control rod reactor shutdown. control rods is in movement compliance with BPWS by a second licensed operator or other qualified member of the technical staff.

E. One or more Reactor Mode E.1 Suspend control rod Immediately Switch - Shutdown Position withdrawal.

channels inoperable.

AND E.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

HATCH UNIT 2 3.3-16 Amendment No. 223

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1(page1of1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Steam Dome Pressure 2 E

2. Reactor Vessel Water Level

a. -317 inches to -17 inches 2 E

b. -150 inches to +60 inches 2 E

c. 0 inches to +60 inches 2 E

d. 0 inches to +400 inches 1 NA

3. Suppression Pool Water Level

a. 0 inches to 300 inches 2 E

b. 133 inches to 163 inches 2 E

4. Drywell Pressure

a. -10 psig to +90 psig 2 E

b. -5 psig to +5 psig 2 E

c. O psig to +250 psig 2 E

5. Drywell Area Radiation (High Range) 2 F

6. Penetration Flow Path Primary Containment Isolation 2 per penetration flow E Valve Position path(a)(b)

7. (Deleted)

8. (Deleted) 2(C) E

9. Suppression Pool Water Temperature 6 E

10. Drywell Temperature in Vicinity of Reactor Level Instrument Reference Leg

11. Diesel Generator (DG) Parameters 1 per DG NA

a. Output Voltage 1 per DG NA

b. Output Current 1 per DG NA

c. Output Power 1 per DG NA

d. Battery Voltage 2 E

12. RHR Service Water Flow (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) Monitoring each of four quadrants.

HATCH UNIT 2 3.3-25 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

N 0 TES-----------------------------------------------------------

1. Penetration flow paths except for 18 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. Functions 2.a, 2.b, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.b, 6.b, 7.a, and 7.b B. --------------N 0 TE-------------- B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Not applicable for capability.

Function 5.c.

One or more automatic Functions with isolation capability not maintained.

C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or B Table 3.3.6.1-1 for the not met. channel.

(continued)

HATCH UNIT 2 3.3-48 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Isolate associated main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced steam line (MSL).

in Table 3.3.6.1-1.

OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by Required E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced penetration flow in Table 3.3.6.1-1. path(s).

G. As required by Required G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action C.1 and referenced penetration flow in Table 3.3.6.1-1. path(s).

H. As required by Required H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced in Table 3.3.6.1-1. AND OR H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and associated Completion Time of Condition F or G not met.

(continued)

HATCH UNIT 2 3.3-49 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I. 1 Declare Standby Liquid 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced Control (SLC) System in Table 3.3.6.1-1. inoperable.

OR 1.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup (RWCU) System.

J. As required by Required J.1 Initiate action to restore Immediately Action C.1 and referenced channel to OPERABLE in Table 3.3.6.1-1. status.

OR J.2 Initiate action to isolate Immediately the Residual Heat Removal (RHR)

Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS

N 0 TES-----------------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

HATCH UNIT 2 3.3-50 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1. 7 ---------------------------N0 TE-------------------------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE In accordance with TIME is within limits. the Surveillance Frequency Control Program HATCH UNIT 2 3.3-51 Amendment No. 223 I

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1 <:: -113 inches Level - Low Low Low, SR 3.3.6.1.2 Level 1 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7

b. Main Steam Line 2 E SR 3.3.6.1.3 <:: 825 psig Pressure - Low SR 3.3.6.1.6

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 s 138% rated Flow- High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1. 7

d. Condenser Vacuum - Low 1, 2 D SR 3.3.6.1.3 <:: 7 inches Hg 2(a), 3(a) SR 3.3.6.1.6 vacuum

e. Main Steam Tunnel 1,2,3 6 D SR 3.3.6.1.1 S194°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

f. Turbine Building Area 1,2,3 16(b) D SR 3.3.6.1.2 s 200°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

2. Primary Containment Isolation

a. Reactor Vessel Water 1,2,3 2 H SR 3.3.6.1.1 <:: 0 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Drywell Pressure -

High 1,2,3 2 H SR 3.3.6.1.1 s 1.92 psig I SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 continued (a) With any turbine stop valve not closed.

(b) With 8 channels per trip string. Each trip string shall have 2 channels per main steam line, with no more than 40 ft separating any two OPERABLE channels.

HATCH UNIT 2 3.3-52 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

2. Primary Containment Isolation (continued)

c. Drywell Radiation - High 1,2,3 F SR 3.3.6.1.1 s 138 R/hr SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

d. Reactor Building Exhaust 1,2,3 2 H SR 3.3.6.1.1 s 80 mR/hr Radiation - High SR 3.3.6.1.3 SR 3.3.6.1.6

e. Refueling Floor Exhaust Radiation - High 1,2,3 2 H SR 3.3.6.1.1 SR 3.3.6.1.3 SR 3.3.6.1.6 s 80 mR/hr I

3. High Pressure Coolant Injection (HPCI) System Isolation

a. HPCI Steam Line Flow - 1,2,3 F SR 3.3.6.1.1 s 303% rated High SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

b. HPCI Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 ~ 100 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

c. HPCI Turbine Exhaust 1,2,3 2 F SR 3.3.6.1.1 s 20 psig Diaphragm Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

d. Drywell Pressure - High 1,2,3 F SR 3.3.6.1.1 s 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

e. HPCI Pipe Penetration Room 1,2,3 F SR 3.3.6.1.1 s 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

f. Suppression Pool Area Ambient 1,2,3 F SR 3.3.6.1.1 s 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 continued HATCH UNIT 2 3.3-53 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 Table3.3.6.1-1 (page3of5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

3. HPCI System Isolation (continued)

g. Suppression Pool Area 1,2,3 F SR 3.3.6.1.4 :s: 16 minutes Temperature - Time Delay SR 3.3.6.1.6 15 seconds Relays

h. Suppression Pool Area 1,2,3 F SR 3.3.6.1.1 :s:42°F Differential Temperature - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

i. Emergency Area Cooler 1,2,3 F SR 3.3.6.1.1 :s: 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line Flow - 1,2,3 F SR 3.3.6.1.1 :s: 307% rated High SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6

b. RCIC Steam Supply Line 1,2,3 2 F SR 3.3.6.1.1 ~ 60 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 C. RCIC Turbine Exhaust 1,2,3 2 F SR 3.3.6.1.1 :s: 20 psig Diaphragm Pressure - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

d. Drywell Pressure - High 1,2,3 F SR 3.3.6.1.1 :s: 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

e. RCIC Suppression Pool 1,2,3 F SR 3.3.6.1.1 :s: 169°F Ambient Area SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

f. Suppression Pool Area 1,2,3 F SR 3.3.6.1.4 :s: 31 minutes Temperature - Time Delay SR 3.3.6.1.6 15 seconds Relays continued)

HATCH UNIT 2 3.3-54 Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

4. RCIC System Isolation (continued)

g. RCIC Suppression Pool 1,2,3 F SR 3.3.6.1.1 :542°F Area Differential SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

h. Emergency Area Cooler 1,2,3 F SR 3.3.6.1.1 s; 169°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

5. RWCU System Isolation

a. Area Temperature - High 1,2,3 1 per area F SR 3.3.6.1.1 s; 150°F SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Area Ventilation 1,2,3 1 per area F SR 3.3.6.1.1 s; 67°F Differential Temperature - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

c. SLC System Initiation 1,2 1(c) SR 3.3.6.1.6 NA

d. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 ;;:: -47 inches Level - Low Low, Level 2 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

6. RHR Shutdown Cooling System Isolation

a. Reactor Steam Dome 1,2,3 F SR 3.3.6.1.1 s; 145 psig Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3,4,5 2(d) J SR 3.3.6.1.1 ;;:: 0 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 (continue )

(c) SLC System Initiation only inputs into one of the two trip systems.

(d) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

HATCH UNIT 2 3.3-55a Amendment No. 223

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 5)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM ALLOWABLE SPECIFIED PER TRIP REQUIRED SURVEILLANCE VALUE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS

7. Traversing lncore Probe System Isolation

a. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 ~ 0 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Drywell Pressure - High 1,2,3 2 G SR 3.3.6.1.1 :s 1.92 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 HATCH UNIT 2 3.3-55b Amendment No. 223

ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure s 150 psig.

ACTIONS

NOTE--------------------------------------------------------

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray subsystem ECCS injection/spray inoperable. subsystem(s) to OPERABLE status.

OR One LPCI pump in both LPCI subsystems inoperable.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 2 3.5-1 Amendment No. 223

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. HPCI System inoperable. C.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means RCIC System is OPERABLE.

AND C.2 Restore HPCI System 14 days to OPERABLE status.

D. HPCI System inoperable. D.1 Restore HPCI System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

AND OR Condition A entered.

D.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem to OPERABLE status.

E. Two or more ADS valves E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

AND OR E.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and dome pressure to associated Completion :s; 150 psig.

Time of Condition C or D not met.

F. Two or more low pressure F.1 Enter LCO 3.0.3. Immediately ECCS injection/spray subsystems inoperable for reasons other than Condition A.

OR HPCI System and two or more ADS valves inoperable.

HATCH UNIT 2 3.5-2 Amendment No. 223

PC IVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------------N 0 TES-----------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment B. --------------N 0 TE--------------- 8.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one two PCIVs. closed and de-activated

automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two PCIVs inoperable except due to leakage not within limit.

(continued)

HATCH UNIT 2 3.6-8 Amendment No. 223

PC IVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE--------------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by excess flow check penetration flow paths with use of at least one valve (EFCV) line and only one PCIV. closed and de-activated penetrations with a

automatic valve, closed closed system manual valve, or blind One or more penetration flange. AND flow paths with one PCIV inoperable except due to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for leakage not within limits. AND EFCV line and penetrations with a C.2 ----------NO TES----------- closed system

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more penetration D.1 Restore leakage to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow paths with leakage not within limit.

within limit.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 2 3.6-9 Amendment No. 223

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.2 ------------------------------N 0 TES---------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside the Surveillance primary containment and not locked, sealed, or Frequency Control otherwise secured and is required to be closed Program during accident conditions is closed.

SR 3.6.1.3.3 -----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside MODE 2 or 3 from primary containment and not locked, sealed, or MODE 4 if primary otherwise secured and is required to be closed containment was during accident conditions is closed. de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe In accordance with (TIP) shear isolation valve explosive charge. the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated, In accordance with automatic PCIV, except for MSIVs, is within limits. the Inservice Testing Program (continued)

HATCH UNIT 2 3.6-11 Amendment No. 223

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion POWER until all Time of Condition A not OPERABLE I RM met. channels s 25/40 divisions of full scale on Range 7.

C. Suppression pool average C.1 Suspend all testing that Immediately temperature> 105°F. adds heat to the suppression pool.

AND Any OPERABLE IRM channel > 25/40 divisions of full scale on Range 7.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool average D.1 Place the reactor mode Immediately temperature> 110°F. switch in the shutdown position.

AND D.2 Determine suppression Once per 30 minutes pool average temperature.

AND D.3 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 2 3.6-22 Amendment No. 223

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool average E.1 Depressurize the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperature> 120°F. reactor vessel to

< 200 psig.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance with within the applicable limits. the Surveillance Frequency Control Program AND 5 minutes when performing testing that adds heat to the suppression pool HATCH UNIT 2 3.6-23 Amendment No. 223

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 -----------------------------N 0 TE-----------------------------

Th e 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 120 seconds using required standby gas Frequency Control treatment (SGT) subsystem(s). Program (continued)

HATCH UNIT 2 3.6-34 Amendment No. 223

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.4.1.4 -----------------------------N 0 TE------------------------------

Th e number of 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 the secondary containment can be In accordance with maintained ;:: 0.20 inch of vacuum water gauge the Surveillance for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using required SGT subsystem(s) at Frequency Control a flow rates 4000 cfm per subsystem. Program HATCH UNIT 2 3.6-35 Amendment No. 223

SC IVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE AL TE RATIONS, During operations with a potential for draining the reactor vessel (OPDRV).

ACTIONS

N0 TES-------------------------------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow paths with one SCIV penetration flow path by inoperable. use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND A.2 -----------NOTES-----------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

(continued)

HATCH UNIT 2 3.6-36 Amendment No. 223

SCI Vs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B. One or more penetration B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow paths with two SCIVs penetration flow path by inoperable. use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and D.1 -------------N 0 TE----------

associated Completion LCO 3.0.3 is not Time of Condition A or B applicable.

not met during movement -------------------------------

of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel during CORE assemblies in the ALTERATIONS, or during secondary containment.

OPDRVs.

(continued)

HATCH UNIT 2 3.6-37 Amendment No. 223

SCI Vs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued)

D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ----------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation In accordance with manual valve and blind flange that is not locked, the Surveillance sealed, or otherwise secured and is required to be Frequency Control closed during accident conditions is closed. Program SR 3.6.4.2.2 Verify the isolation time of each power operated, In accordance with automatic SCIV is within limits. the Surveillance Frequency Control Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to the In accordance with isolation position on an actual or simulated the Surveillance actuation signal. Frequency Control Program HATCH UNIT 2 3.6-38 Amendment No. 223

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required Unit 2 SGT B.1 Restore required SGT 7 days subsystem inoperable. subsystem to OPERABLE status.

OR One required Unit 1 SGT subsystem inoperable for reasons other than Condition A.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and ------------------N 0 TE-----------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A or B -------------------------------------------

not met during movement of irradiated fuel D.1 Place remaining Immediately assemblies in the OPERABLE SGT secondary containment, subsystem(s) in during CORE operation.

ALTERATIONS, or during OPDRVs. OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

(continued)

HATCH UNIT 2 3.6-40 Amendment No. 223

AC Sources - Operating 3.8.1 ACTIONS

NOTE--------------------------------------------------------

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuits. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery feature(s) with no offsite of no offsite power to power available one 4160 V ESF bus inoperable when the concurrent with redundant required inoperability of feature(s) are redundant required inoperable. feature(s)

AND A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status.

B. One Unit 2 or the swing DG B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

HATCH UNIT 2 3.8-2 Amendment No. 223

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 (continued) AND 14 days for the swing diesel with maintenance restrictions met C. One required Unit 1 DG C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s), supported by discovery the inoperable DG, of Condition C inoperable when the concurrent with redundant required inoperability of feature(s) are redundant required inoperable. feature(s)

AND C.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR C.3.2 Perform SR 3.8.1.2.a for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

(continued)

HATCH UNIT 2 3.8-4 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 ----------------------------N 0 TE-------------------------------

T his Surveillance shall not normally be performed in MODE 1 or 2. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of unit power In accordance with supply from the normal offsite circuit to the the Surveillance alternate offsite circuit. Frequency Control Program SR 3.8.1.7 ----------------------------N 0 TES-----------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2, except for the swing DG. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. For the swing DG, this Surveillance shall not be performed in MODE 1 or 2 using the Unit 2 controls.

Credit may be taken for unplanned events that satisfy this SR.

2. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG rejects a load greater than or In accordance with equal to its associated single largest post-accident the Surveillance load, and: Frequency Control Program

a. Following load rejection, the frequency is s 65.5 Hz; and

b. Within 3 seconds following load rejection, the voltage is;;:: 3740 V ands 4580 V.

(continued)

HATCH UNIT 2 3.8-10 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.8 -----------------------------N 0 TES----------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2, except for the swing DG. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. For the swing DG, this Surveillance shall not be performed in MODE 1 or 2 using the Unit 2 controls.

Credit may be taken for unplanned events that satisfy this SR.

2. If grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

3. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factors 0.88 In accordance with does not trip and voltage is maintained s 4800 V the Surveillance during and following a load rejection of~ 2775 kW. Frequency Control Program (continued)

HATCH UNIT 2 3.8-11 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.9 ----------------------------N 0 TES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite In accordance with power signal: the Surveillance Frequency Control

a. De-energization of emergency buses; Program

b. Load kdding from emergency buses; and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in s 12 seconds,

2. Energizes auto-connected shutdown loads through automatic load sequence timing devices,

3. Maintains steady state voltage

3740 V ands; 4243 V,

4. Maintains steady state frequency

58.8 Hz and s 61.2 Hz, and

5. Supplies permanently connected and auto-connected shutdown loads for ;:; 5 minutes.

(continued)

HATCH UNIT 2 3.8-12 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.10 ---------------------------N 0 TES----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core In accordance with Cooling System (ECCS) initiation signal each DG the Surveillance auto-starts from standby condition and: Frequency Control Program

a. Ins 12 seconds after auto-start achieves voltage~ 3740 V, and after steady state conditions are reached, maintains voltage

~ 3740 V ands 4243 V;

b. Ins 12 seconds after auto-start achieves frequency ~ 58.8 Hz, and after steady state conditions are reached, maintains frequency ~ 58.8 Hz and s 61.2 Hz; and

c. Operates for ~ 5 minutes.

(continued)

HATCH UNIT 2 3.8-13 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.11 --------------------------N 0 TE---------------------------------

Th is Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG's non-critical automatic trips are In accordance with bypassed on actual or simulated loss of voltage the Surveillance signal on the emergency bus concurrent with an Frequency Control actual or simulated ECCS initiation signal. Program (continued)

HATCH UNIT 2 3.8-14 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.12 ---------------------------NOTES------------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2, unless the other two DGs are OPERABLE. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. If either of the other two DGs becomes inoperable, this Surveillance shall be suspended.

Credit may be taken for unplanned events that satisfy this SR.

3. If grid conditions do not permit, the power factor limit is not required to be met. Under this condition, the power factor shall be maintained as close to the limit as practicable.

4. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG operating at a power factors 0.88 In accordance with operates for <! 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: the Surveillance Frequency Control

a. For<! 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2: 3000 kW; and Program

b. For the remaining hours of the test loaded

<! 2775 kW and s 2825 kW.

(continued)

HATCH UNIT 2 3.8-15 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 ---------------------------NOTES------------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded

~ 2565 kW. Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. For the swing DG, a single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in In accordance with

12 seconds, voltage ~ 37 40 V and frequency the Surveillance

~ 58.8 Hz; and after steady state conditions are Frequency Control reached, maintains voltage~ 3740 V and::;; 4243 V Program and frequency~ 58.8 Hz and ::;; 61.2 Hz.

SR 3.8.1.14 ---------------------------N 0 TE--------------------------------

Th is Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG: In accordance with the Surveillance

a. Synchronizes with offsite power source Frequency Control while loaded with emergency loads upon a Program simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

(continued)

HATCH UNIT 2 3.8-16 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 ---------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify with a DG operating in test mode and In accordance with connected to its bus, an actual or simulated ECCS the Surveillance initiation signal overrides the test mode by: Frequency Control Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.16 -----------------------------NOTE------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block In accordance with is within 10% of design interval for each load the Surveillance sequence timing device. Frequency Control Program (continued)

HATCH UNIT 2 3.8-17 Amendment No. 223

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.17 ----------------------------N 0 TES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated ECCS initiation signal: Frequency Control Program

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. Energizes permanently connected loads in ::; 12 seconds,

2. Energizes auto-connected emergency loads through automatic load sequence timing devices,

3. Achieves steady state voltage

~ 3740 V and::; 4243 V,

4. Achieves steady state frequency

~ 58.8 Hz and::; 61.2 Hz, and

5. Supplies permanently connected and auto-connected emergency loads for ~ 5 minutes.

(continued)

HATCH UNIT 2 3.8-18 Amendment No. 223

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.4.7 -----------------------------N 0 TES----------------------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3, except for the swing DG battery. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required the Surveillance emergency loads for the design duty cycle when Frequency Control subjected to a battery service test. Program (continued)

HATCH UNIT 2 3.8-29 Amendment No. 223

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.8 -------------------------------N 0 TE----------------------------

Th is Surveillance shall not normally be performed in MODE 1, 2, or 3, except for the swing DG battery. However, portions of the surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is ;;:: 80% of the In accordance with manufacturer's rating when subjected to a the Surveillance performance discharge test or a modified Frequency Control performance discharge test. Program 12 months when battery shows degradation or has reached 85% of expected life with capacity < 100% of manufacturer's rating 24 months when battery has reached 85% of expected life with capacity ;;:: 100% of manufacturer's rating SR 3.8.4.9 For required Unit 1 DC sources, the SRs of Unit 1 In accordance with Specification 3.8.4 are applicable. applicable SRs HATCH UNIT 2 3.8-30 Amendment No. 223

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more (Unit 2 or B.1 Restore DG DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months swing bus) DG DC electrical power electrical power distribution distribution subsystem subsystems inoperable. to OPERABLE status.

C. One or more (Unit 2 or C.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months swing bus) AC electrical power distribution power distribution subsystem to subsystems inoperable. OPERABLE status.

D. One Unit 2 station service D.1 Restore Unit 2 station 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power service DC electrical distribution subsystem power distribution inoperable. subsystem to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND or D not met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two or more electrical F.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

HATCH UNIT 2 3.8-38 Amendment No. 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary as follows:

1) For noble gases, less than or equal to a dose rate of 500 mrem/year to the total body and less than or equal to a dose rate of 3000 mrem/year to the skin, and

2) For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, less than or equal to a dose rate of 1500 mrem/year to any organ;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives> 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

(continued)

HATCH UNIT 2 5.0-9 Amendment No. 223

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Component Cyclic or Transient Limit This program provides controls to track FSAR Section 5.2, cyclic and transient occurrences, to ensure that reactor coolant pressure boundary components are maintained within the design limits.

5.5.6 lnservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports.

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda are as follows:

ASME Boiler and Pressure Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing lnservice lnservice Testing Activities Testing Activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days

b. The provisions of SR 3.0.2 are applicable to the frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

5.5.7 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2, Sections C.5.c and C.5.d, and in accordance with Regulatory Guide 1.52, Revision 2.

(continued)

HATCH UNIT 2 5.0-10 Amendment No. 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

The program shall include:

a. The limits for the concentrations of hydrogen in the main condenser offgas treatment system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. An API gravity or an absolute specific gravity within limits,

2. A flash point and kinematic viscosity within limits for ASTM 20 fuel oil, and

3. A water and sediment content within limits;

b. Within 31 days following addition of the new fuel oil to storage tanks, verify that the properties of the new fuel oil, other than those addressed in a., above, are within limits for ASTM 20 fuel oil; and (continued)

HATCH UNIT 2 5.0-13 Amendment No. 223

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Diesel Fuel Oil Testing Program (continued)

c. Total particulate concentration of the fuel oil is :::; 10 mg/liter when tested every 92 days.