NLS2018063, Submittal of 10 CFR 50.55a Relief Request PR5-02 Supplement

Submittal of 10 CFR 50.55a Relief Request PR5-02 Supplement

ML18319A095
Person / Time
Site:	Cooper
Issue date:	11/08/2018
From:	Dent J Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2018063
Download: ML18319A095 (7)

Text

Nebraska Public Power District NLS2018063 November 8, 2018 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Always there when you need us

Subject:

10 CFR 50.55a Relief Request PR5-02 Supplement Cooper Nuclear Station, Docket No. 50-298, DPR-46 10 CFR 50.55a

Reference:

Letter NLS2018061 dated November 5, 2018, from John Dent, Jr., Nebraska Public Power District (NPPD) to Nuclear Regulatory Commission (NRC),

"10CFR 50.55a Relief Request PR5-02"

Dear Sir or Madam:

The purpose of this letter is for NPPD to supplement the emergent relief request made on November 5, 2018 (Reference).

Relief Request PR5-02 will be used only for the duration of Refueling Outage 30. The information requested by the NRC in relation to the referenced letter was provided via email on November 5, 2018. This same information is attached to this letter.

This letter contains no regulatory commitments.

Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

Sincerely,

~1ff£1<- ~

/w?" ~J f1"' ~

John Dent, Jr.

Vice President Nuclear and Chief Nuclear Officer

/tf

Attachment:

Cooper Nuclear Station Relief Request PR5-02 Supplemental Information COOPER NUCLEAR STATION P.O. Box 98 /Brownville,. NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

NLS2018063 Page 2 of2 cc: Regional Administrator w/attachment USNRC - Region IV Cooper Project Manager w/attachment USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/attachment USNRC-CNS NPG Distribution w/o attachment CNS Records w/attachment

NLS2018063 Attachment Page 1 of 5 Cooper Nuclear Station Relief Request PRS-02 Supplemental Information Cooper Nuclear Station (CNS) understands that the relief being requested is applicable only to Refueling Outage 30 and not for the entirety of the fifth 10 year inservice inspection interval. Any additional period(s) outside of CNS Refueling Outage 30 would require subsequent, stand-alone, relief requests.

The specific components for which relief is being requested are listed in the tables on the next page.

Drawings describing the location of the components for which relief is being requested have also been included as part of this attachment.

For the portions of piping operated at or above reactor pressure during normal operation that are not at test pressure, defense-in-depth for detection of possible through-wall leakage is provided by the following:

The temperature alarm subsystem of leak detection system is comprised of temperature sensing elements installed in the vicinity of residual heat removal (RHR), reactor water cleanup (RWCU), high pressure coolant injection (HPCI),

reactor core isolation cooling (RCIC), and main steam lines (MS), and temperature switches that actuate annunciators in the Control Room. It is designed to detect leaks in the major steam piping system, especially in remote or enclosed areas such as the steam tunnel. If a steam or water leak occurs, the temperature element would sense a rise in ambient temperature and cause an alarm in the Control Room. In addition, the continuous temperature signals are transmitted to Plant Management Information System (PMIS) for Safety Parameter Display System (SPDS) display.

Control Room operators monitor Main Steam Tunnel temperatures twice per shift (every six hours) and record in Operations Log when temperature exceeds 160 F.

Drywell unidentified and identified leak rates are monitored in accordance with Operations daily surveillance log every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

NLS2018063 Attachment Page 2 of 5 CNS PRS-02 Lists of Components Valves not in position required for normal reactor startup:

Position Required Valve Description for Normal Reactor Startup RF-CV-13CV Outboard Feedwater Open Check Valve RF-CV-14CV Inboard Feedwater Open Check Valve RF-CV-15CV Outboard Feedwater Open Check Valve Outboard Main MS-AOV-A086A Steam Isolation Open Valve Outboard Main MS-AOV-A086B Steam Isolation Open Valve Outboard Main MS-AOV-A086C Steam Isolation Open Valve Outboard Main MS-AOV-A086D Steam Isolation Open Valve HPCI-MOV-M015 Inboard HPCI Steam Open Supply HPCI-MOV-M016 Outboard HPCI Open Steam Supply RCIC-MOV-M015 Inboard RCIC Steam Open Supply RCIC-MOV-M016 Outboard RCIC Open Steam Supply Other valves discussed in Relief Request:

Position Required Valve Description for Normal Reactor Startup MS-MOV-M074 Inboard Main Steam Open/Closed Drain Valve MS-MOV-M077 Outboard Main Open/Closed Steam Drain Valve HPCI-CV-29CV HPCI Injection Check Closed Valve RF-CV-16CV Inboard Feedwater Open Check Valve Position During System Leakage Test Closed Closed Closed Closed Closed Closed Closed Closed Closed Closed Closed Position During System Leakage Test Open Open/Closed Closed Open

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NJTHORJZED CONflGURATION PER EE03-72.

111. INDICATIONS ARE Al.SO AVAIL.ABLE IN THE ~

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(Rff: 71i11E271 SH e)

AS BUILT 454003637 STATUS: RitleoN STATUS 0.-.TE: 10/J0/ 20UI OS APPftOYCD: Gt..H,tr£lt.£ VER: M, RtV: 79 SIZE: F FLOW DIAGRA~ -

HIGH PRESSURE COOLANT INJECTION AND REACTOR FEED SYSTE~S COOPER NUCLEAR STATION BURNS & ROE i l---=:J!!l!!!'=-.L._~~~---1~§ 2044 I

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