LIC-15-0018, Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-5

Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-5

ML15027A622
Person / Time
Site:	Fort Calhoun
Issue date:	01/27/2015
From:	Simpkin T Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR 14-03, LIC-15-0018
Download: ML15027A622 (3)

Text

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u;;;;u Omaha Public Power Dis/riel 444 South 1ffh Street Mall Omaha, NE 68102-2247 LIC-15-0018 10 CFR 50.90 January 27, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285

Subject:

Supplement to License Amendment Request (LAR) 14-03; Proposed Change to Technical Specification 3.2, Table 3-5

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),

"License Amendment Request (LAR) 14-03, Proposed Change to Technical Specification 3.2, Table 3-5," dated April 30, 2014 (ML14125A239) (LIC 0041)

2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort Calhoun Station, Unit No.1 - Issuance of Amendment RE: Revise Technical Specification Surveillance Requirement for the Pressurizer Safety Valves to be Consistent with the lnservice Testing Program (TAC NO. MF3466)

The purpose of this letter is to supplement LAR 14-03 (Reference 1) with new clean Technical Specification (TS) pages. As submitted in Referenced 1, the High Pressure Safety Injection (HPSI) Throttle Valves were slated to become Item 25 in Table 3-5. However, Amendment No.

274 (Reference 2) issued on November 6, 2014 added River Level as Item 25 in Table 3-5.

Therefore, as shown in the attached pages, the HPSI Throttle Valves become Item 26.

There are no regulatory commitments contained within this letter.

If you should have any questions regarding this submittal or require additional information, please contact Mr. Bill R. Hansher at (402) 533-6894.

Respectfully,

• ~

~e W. Simpkin Manager, Site Regulatory Assurance TWS/mle

Attachment:

Clean TS Pages Employment with Equal Opportunity

TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests (continued)

Table 3-5, Item 8b verifies that primary to secondary LEAKAGE is less or equal to 150 gallons per day through any one SG. Satisfying the primary to secondary LEAKAGE limit ensures that the operational LEAKAGE performance criterion in the Steam Generator Program is met. If this surveillance requirement is not met, compliance with LCO 3.17, "Steam Generator Tube Integrity," should be evaluated. The 150 gallons per day limit is measured at room temperature as described in Reference 5. The operational LEAKAGE rate limit applies to LEAKAGE through any one SG. If it is not practical to assign the LEAKAGE to an individual SG, all the primary to secondary LEAKAGE should be conservatively assumed to be from one SG.

The Surveillance is modified by a footnote which states that the Surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation. For RCS primary to secondary LEAKAGE determination, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows.

The Surveillance Frequency of daily is a reasonable interval to trend primary to secondary LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents. The primary to secondary LEAKAGE is determined using continuous process radiation monitors or radiochemical grab sampling in accordance with the EPRI guidelines (Ref. 5).

Table 3-5, Item 25 verifies adequate measurements are taken to ensure that facility protective actions will be taken (and power operation will be terminated) in the event of high and/or low river level conditions.

The high river level limit of less than 1004 feet mean sea level is based on the maximum elevation at which facility flood control measures provide protection to safety related equipment (i.e., due to restricted access/egress to the intake structure veranda once the flood barriers are installed prior to river level reaching 1004 feet msl). A continuous watch will be established at 1002 feet mean sea level to provide adequate response time for rising river levels in accordance with the abnormal operating procedure. The river level surveillance requirement specified also ensures sufficient net positive suction head is available for operating the RW pumps. The minimum river level of 976 feet 9 inches provides adequate suction to the RW pumps for cooling plant components. The surveillance frequency of "Daily" is a reasonable interval and models guidance provided in NUREG-0212, Revision 2, "Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors," Section 4.7.6. This surveillance requirement verifies that the Missouri River water level is maintained at a level greater than or equal to 976 feet 9 inches mean sea level. A continuous watch is established to monitor the river level when the river level reaches 980 feet mean sea level to assure no sudden loss of water supply occurs.

Table 3-5, Item 26 verifies the proper position of stops on high pressure safety injection system valves.

The valves have stops to position them properly so that flow is restricted to a ruptured cold leg, ensuring that the other cold legs receive at least the required minimum flow. The refueling frequency is based on the need to perform these Surveillances under the conditions that apply during a plant outage and the potential for unplanned transients if the Surveillances were performed with the reactor at power.

References

1) USAR, Section 9.10

2) ASTM 04057, ASTM 0975, ASTM 04176, ASTM 02622, ASTM 0287, ASTM 6217, ASTM 02709

3) ASTM 0975, Table 1

4) Regulatory Guide 1.137

5) EPRI, "Pressurized Water Reactor Primary-to-Secondary Leak Guidelines."

3.2- Page 5 Amendment No. 229,246,2&7, 274 Tssc-oe ooa o, 14 oo1 o, 14 ooa o

TECHNICAL SPECIFICATIONS TABLE3-5 MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test Frequency Reference

25. River Level Verify water level is within limits by measurement D 9.8 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when the water level is less than 1004 feet and greater than or equal to 976 feet 9 inches above mean sea levels.

26. HPSI Throttle Valves Verify, for each HPSI throttle valve listed R below, each position stop is in the correct position .

HCV-311 HCV-312 HCV-314 HCV-315 HCV-317 HCV-318 HCV-320 HCV-321 1

The provisions of Technical Specification 3.0.1 and 3.0.5 do not apply.

2 Whenever the system is at or above operating temperature and pressure.

3 Not applicable to primary to secondary LEAKAGE.

4 Verify primary to secondary LEAKAGE is s 150 gallons per day through any one SG. This surveillance is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

5 Tests shall be performed in accordance with applicable section(s) of ANSI N510-1980.

3.2- Page 14 Amendment No. 188,221, 2a9,249,267, 274,

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