ML073320373

Technical Specifications for Edwin I. Hatch Nuclear Plant, Units 1 and 2, Issuance of Amendments Regarding Control Rod Scram Time Testing Frequency (TAC MD5722 and MD5723)

ML073320373
Person / Time
Site:	Hatch
Issue date:	11/26/2007
From:	Martin R NRC/NRR/ADRO/DORL/LPLII-1
To:	Madison D Southern Nuclear Operating Co
Martin R, NRR/DORL, 415-1493
Shared Package
Ml073170098	List: ML073320373
References
TAC MD5722, TAC MD5723
Download: ML073320373 (6)

Text

for sample analysis or instrument 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 ncle-ar 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 state reactor core power levels not Inexcess of 2804 megawatts thermal.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 2 5 4 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 fisted below, Isnot required to be performed Immediately upon Implementation of Amendment No. 195. The SR fisted below shall be successfully demonstrated prior to 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 Ineffect all provisions of the fire protection program, which Is referenced in the Updated Final Safety Analysis Report for the facility, as contained Inthe updated Fire Hazards Analysis and Fire Protection Program for 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 ifthe changes Renewed License No. DPR-57 Amendment No. 2 5 4

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY 4.

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 fuel pressure a 800 psig. movement within the reactor pressure vessel AND Prior to exceeding 40% RTP after each reactor shutdown

> 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 200 days I control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in

,> 800 psig. MODE 1 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 steam dome pressure > 800 psig. work on control rod or CRD System that could affect scram time HATCH UNIT 1 3.1-10 Amendment No. 2_54

Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.1 (continued)

REQUIREMENTS acceptable scram times for the transients analyzed in References 3 and 4.

Maximum scram insertion times occur at a reactor steam dome pressure of approximately 800 psig because of the competing effects of reactor steam dome pressure and stored accumulator energy.

Therefore, demonstration of adequate scram times at reactor steam dome pressure > 800 psig ensures that the measured scram times will be within the specified limits at higher pressures. Limits are specified as a function of reactor pressure to account for the sensitivity of the scram insertion times with pressure and to allow a range of pressures over which scram time testing can be performed. To ensure that scram time testing is performed within a reasonable time following fuel movement within the reactor pressure vessel or after a shutdown

> 120 days or longer, control rods are required to be tested before exceeding 40% RTP. In the event fuel movement is limited to selected core cells, it is the intent of this SR that only those CRDs associated with the core cells affected by the fuel movements are required to be scram time tested. This Frequency is acceptable considering the additional surveillances performed for control rod OPERABILITY, the frequent verification of adequate accumulator pressure, and the required testing of control rods affected by work on control rods or the CRD System.

SR 3.1.4.2 Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 7.5% of the control rods in the sample tested are determined to be "slow". With more than 7.5% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 7.5%

criterion (i.e., 7.5% of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all Surveillances) exceeds the LCO limit. For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 200 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances (continued)

HATCH UNIT 1 B 3.1-22 Amendment No. 254

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(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.

.0. 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 6f the Commission now or hereafter in effect; and the additional conditions2 specified or Incorporated below.

(1) Maximum Power Level Southern Nuclear Is authorized to operate the facility at steady state reactor core power levels not Inexcess 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., 19 8 are hereby Incorporated In the renewed license. Southern Nuclear shala 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 Ineffect all provisions of the fire protection program, which is referenced in the the Updated Final Safety Analysis Report for the facility, as contained 2The original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

Renewed Ucense No. NPF-5 Amendment No. 19 8

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS

---

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

During single control rod scram time Surveillances, the control rod drive. (ORD) 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 fuel pressure > 800 psig. movement within the reactor pressure vessel AND Prior to exceeding 40% RTP after each reactor shutdown

> 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 200 days I control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in z 800 psig. MODE 1 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 steam dome pressure - 800 psig. work on control rod or CRD System that could affect scram time HATCH UNIT 2 3.1-10 Amendment No. 19 8

Control Rod Scram Times B 3.1.4 BASES SURVEILLANCE SR 3.1.4.1 (continued).

REQUIREMENTS acceptable scram times for the transients analyzed in References 3 and 4.

Maximum scram insertion times occur at a reactor steam dome pressure of approximately 800 psig because of the competing effects of reactor steam dome pressure and stored accumulator energy.

Therefore, demonstration of adequate scram times at reactor steam dome pressure > 800 psig ensures that the measured scram times will be within the specified limits at higher pressures. Limits are specified as a function of reactor pressure to account for the sensitivity of the scram insertion times with pressure and to allow a range of pressures over which scram time testing can be performed. To ensure that scram time testing is performed within a reasonable time following fuel movement within the reactor pressure vessel or after a shutdown 120 days or longer, control rods are required to be tested before exceeding 40% RTP. In the event fuel movement is limited to selected core cells, it is the intent of this SR that only those CRDs associated with the core cells affected by the fuel movements are required to be scram time tested. This Frequency is acceptable considering the additional surveillances performed for control rod OPERABILITY, the frequent verification of adequate accumulator pressure, and the required testing of control rods affected by work on control rods or the CRD System.

SR 3.1.4.2 Additional testing of a sample of control rods is required to verify the continued performance of the scram function during the cycle. A representative sample contains at least 10% of the control rods. The sample remains representative if no more than 7.5% of the control rods in the sample tested are determined to be "slow". With more than 7.5% of the sample declared to be "slow" per the criteria in Table 3.1.4-1, additional control rods are tested until this 7.5%

criterion (i.e., 7.5% of the entire sample size) is satisfied, or until the total number of "slow" control rods (throughout the core, from all Surveillances) exceeds the LCO limit. For planned testing, the control rods selected for the sample should be different for each test. Data from inadvertent scrams should be used whenever possible to avoid unnecessary testing at power, even if the control rods with data may have been previously tested in a sample. The 200 day Frequency is based on operating experience that has shown control rod scram times do not significantly change over an operating cycle. This Frequency is also reasonable based on the additional Surveillances (continued)

HATCH UNIT 2 B 3.1-22 Amendment No. 198