NLS2015055, Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
| ML15132A652 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/04/2015 |
| From: | Limpias O Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2015055 | |
| Download: ML15132A652 (5) | |
Text
N Nebraska Public Power District Always there when you need us 50.90 NLS2015055 May 4, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46
Reference:
Letter from Oscar A. Limpias, Nebraska Public Power District, to U.S. Nuclear Regulatory Commission dated January 15, 2015, "License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function" (NLS2014087) (ML 15021 A27)
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District to correct an error on a Technical Specifications (TS) page submitted with the proposed referenced amendment to add new section, TS 3.6.1.9, Residual Heat Removal Containment Spray, and add related drywell pressure switches to TS 3.3.5.1, Emergency Core Cooling System Instrumentation.
The proposed License Amendment Request (LAR) contains an error associated with the changes requested to Table 3.3.5.1 -1, Emergency Core Cooling System Instrumentation on TS page 3.3-
- 39. The proposed LAR relocates the Containment Pressure-High instrument from the Technical Requirements Manual (TRM) to the TS Section 3.3.5.1, Table 3.3.5.1-1 Function 2.h. In the proposed LAR it is shown that Surveillance Requirement 3.3.5.1.4 is correctly applied to this function, but inappropriately indicates that footnotes (c) and (d) are applicable for this function.
Footnotes (c) and (d) to Table 3.3.5.1-1 were specifically added by TS Amendment 242, Implementation of 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option A (TAC No. ME7169) for other functions in the table. TSTF-493, Revision 4, is titled "Clarify Application of Setpoint Methodology for LSSS Functions." The Containment Spray function, which is being relocated to the TS, is not considered a Limiting Safety System Setting (LSSS) as there is no Safety Limit established for this function. Those functions that have been identified as LSSS functions are listed in TRM Section T5.14 and the Containment Pressure-High function associated with the Containment Spray Permissive is not one of those functions listed.
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com
Based on the above, footnotes (c) and (d) do not apply to Table 3.3.5.1-1, Function 2.h and should be removed. The attachment to this letter includes a corrected marked up version of TS page 3.3-39 and a corrected final typed version of TS page 3.3-39 to be used by the Nuclear Regulatory Commission (NRC) in their review of the previously submitted LAR.
The change to the TS page neither impacts the conclusions of the no significant hazards consideration evaluation that was performed pursuant to 10 CFR 50.91 (a)(1), nor the environmental consideration performed pursuant to 10 CFR 51.22.
No formal licensee commitments are being made in this letter.
By copy of this letter and its attachments, the appropriate State of Nebraska official is notified in accordance with 10 CFR 50.91 (b)(1). Copies are also provided to the NRC Region IV office and the Senior Resident Inspector in accordance with 10 CFR 50.4(b)(1).
Should you have any question concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on (D te)
O's64r A. Limpiag Vice President - Nuclear and Chief Nuclear Officer
/dv
Attachment:
Corrected Mark Up and Final Typed Technical Specifications Page 3.3-39 cc: Regional Administrator w/attachment NPG Distribution w/o attachment USNRC - Region IV Senior Resident Inspector w/attachment CNS Records w/attachment USNRC - CNS Nebraska Health and Human Services w/attachment Department of Regulation and Licensure Cooper Project Manager w/attachment USNRC - NRR Project Directorate IV-1
NLS2015055 Attachment Page 1 of 3 Attachment Corrected Mark Up and Final Typed Technical Specifications Page 3.3-39 Cooper Nuclear Station, NRC Docket No. 50-298, License No. DPR-46
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)
Emergency Core Cooling System instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.t REQUIREMENTS VALUE
. 2-LPCI System (continued) 1,2..
- h. Containment Coolant Injection 4 (a).
Pressure - High Pump Discharge Fl"
. Low (gypass)
- 3.
High Pressure Coolant Injection (HPCI) System
- a.
Reactor Vessel 1
Water Level - Low Low (Level 2) 20), 3
- 3.
1 per 5(a) subsystem E
,*ItV7 n
1"4(C)(d)
PI 3.5.1.
> 2 psigI SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 4
Mtf b-Drywell Pressure -
High
- c.
Reactor Vessel Water Level - High (Level 8)
- d.
Emergency Condensate Storage Tank (ECST) Level -
Low
- e.
Suppression Pool Water Level-High 1.
2() V) 1.
1,
2(r. 30 1.,
2 (f).
4 2
2 2
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1,4(c)(d)
SR 3-3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3,3.5.1.4 SR 3.3.5.1.5 o
SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.5 O
SR 3.3.5.12 SR 3.3.5.1.4 SR 3.3.5.1.5
< 1.84 psig
-e 54 inches t 23 inches
-42 inches I
<4 inches (continued)
(a)
When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.
(c)
If the as-found channel selpolnt is outside Its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(d)
The instrument channel selpoint shall be reset to a value that is within the asleft tolerance around the Umiting Trip Setlpoint (LTSP) at the completion of the surveilance; otherwise, the channel shalg be declared inoperable. Setpainls mom conservative than the LTSP am acceptable proviled that the as-found and as-left tolerances a"pfy to the actual seiloant implemented In the Surveillance procedures (Nominal Trip Selpoint) to confirm channel performanc.
The Liriting Trip Setpoint and the methodologies used to determine the as-found and the as-left tolerances are speciffed in the Technical Requirements Manual.
(IM With reactor steam dome pressure > 150 psig.
Cooper 3.3-39 Amendment No.-242-
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 2.
LPCI System (continued)
- g.
Low Pressure Coolant 1,2,3, 1 per subsystem E
> 2107 gpm Injection Pump Discharge SR 3.3.5.1.4(cxd)
Flow - Low (Bypass) 4(a), 5(a)
- h.
Containment Pressure -
1,2,3 4
> 2 psig High SR 3.3.5.1.4 SR 3.3.5.1.5
- 3.
High Pressure Coolant Injection (HPCI) System
- a.
4 B
> -42 inches
- Low Low (Level 2)
SR 3.3.5.1.2 2(f, 3(f SR 3.3.5.1.4(cXd)
- b.
Drywell Pressure - High 1,
4 B
< 1.84 psig SR 3.3.5. 1.4(cXd) 2(), 3(f SR 3.3.5.1.5
2 C
<*54 inches
- High (Level 8)
SR 3.3.5.1.2 SR 3.3.5.1.4 2(0, 3S)
- d.
Emergency Condensate 1,
2 D
> 23 inches Storage Tank (ECST) Level -
SR 3.3.5.1.3 Low 2(0, 3(f SR 3.3.5.1.5
- e. Suppression Pool Water 1,
2 D
<4 inches Level - High SR 3.3.5.1.4 2(0, 3(f SR 3.3.5.1.5 (continued)
(a) When the associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.
(c) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Limiting Trip Setpoint (LTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the LTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (Nominal Trip Setpoint) to confirm channel performance. The Limiting Trip Setpoint and the methodologies used to determine the as-found and the as-left tolerances are specified in the Technical Requirements Manual.
(f) With reactor steam dome pressure >150 psig.
Cooper 3.3-39 Amendment No.