AEP-NRC-2016-14, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation

Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation

ML16028A144
Person / Time
Site:	Cook
Issue date:	01/21/2016
From:	Lies Q Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2016-14, CAC MF6984
Download: ML16028A144 (8)

Text

MINDIANA Indiana Michigan Power MICHIGANCook Nuclear Plant JJV*I*'R One Cook Place A untof~nerian lectic PwerBridgmnan, Ml49106 A unt ofmenan Eectic PwerIndiana Michigan Powercomn January 21, 2016 AEP-NRC-201 6-14

• 10 CER 50.90 Docket Nos. 50-316 U. S. Nuclear Regulatory Commission ATT-IN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation

References:

1. Letter from Q. S. Lies, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Unit 2 License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation," dated October 19, 2015, Agencywide Documents Access and Management System (ADAMS) Accession No. ML15293A497.

2. E-mail capture from A. W. Dietrich, NRC, to H. L. Kish, I&M, "D.C. Cook Nuclear Plant, Unit 2-SBPB Request for Additional Information Concerning ESFAS [AR (CAC No. MF6984),"

dated December 10, 2015, ADAMS Accession No. ML15344A350.

This letter provides Indiana Michigan Power Company's (l&M), licensee for Donald C. Cook Nuclear Plant (CNP) Unit 2, response to the Request for Additional Information (RAI) by the U. S. Nuclear Regulatory Commission (NRC) regarding a license amendment request (LAR) to revise Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.

By Reference 1, I&M submitted a request to amend the TSs to CNP Unit 2 Renewed Facility Operating License DPR-74. I&M proposes to modify TS 3.3.2 requirements for the ESFAS instrumentation by adding a new Condition for inoperable required channels for main feedwater pump trips, and by adding a footnote to- the Applicable Mode column of TS Table 3.3.2-1 to reflect applicability in Mode 2. By Reference 2, the NRC transmitted an RAI from the Balance of Plant Branch regarding the [AR submitted by l&M in Reference 1.

Enclosure I to this letter provides an affirmation statement. Enclosure 2 to this letter provides I&M's response to the NRC's RAI in Reference 2. Copies of this letter are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality, in accordance with the requirements of 10 CFR 50.91.

U. S. Nuclear Regulatory Commission AEP-NRC-2016-14 Page 2 There are no new regulatory commitments made in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.

Sincerely, Q. ~Shane Lies Site Vice President TLC/mll

Enclosures:

1. Affirmation

~Response to Request for Additional Information Regarding the License Amendment 2....

Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation

3. Donald C. Cook Nuclear Plant Unit 2 Technical Specification (TS) Page 3.3.2-3 Marked to Show Proposed Changes TS 3.3.2, ESFAS Instrumentation c: R. J. Ancona, MPSC A. W. Dietrich, NRC, Washington, D.C.

MDEO - RMD/RPS NRC Resident Inspector C. D. Pederson, NRC, Region Ill A. J. 'Williamson, AEP Ft. Wayne, w/o enclosures

Enclosure 1 to AEP-NRC-2016-14 AFFIRMATION of Indiana Michigan I, Q. Shane Lies, being duly sworn, state that I am the Site Vice President with the U. S. Nuclear Power Company (I&M), that I am author-ized to sign and file this request and the matters set Regulatory Commission on behalf of I&M, and that the statements made information, and forth herein pertaining to I&M are true and correct to the best of my knowledge, belief.

Indiana Michigan Power Company Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIIS' \ DAY O F',,.¢ ,4, 2016 NotaryDANIELLE BURGOYNE Public, State of Michigan County of Berrien .

My commission Expires 04-04-2018 Acting In the County ot'*S5~X Mv Commission Expires *Z~- (>\ -~ *-,\

Enclosure 2 to AEP-NRC-2016-14 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation By letter dated October 19, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15293A497) (Reference 1), Indiana Michigan Power Company (I&M), the licensee for the Donald C. Cook Nuclear Plant (CNP), Unit 2, submitted a license amendment request (LAR). The proposed amendment would modify Technical Specifications (TS) 3.3.2 requirements for the Engineered Safety Feature Actuation System (ESFAS) instrumentation by adding a new Condition for inoperable required channels for main feedwater (MFVW) pump trips, and by adding a footnote to the Applicable Mode column of TS Table 3.3.2-1 to reflect applicability in Mode 2.-

The U. S. Nuclear Regulatory Commission (NRC) staff in the Balance of Plant Branch (SBPB) of the Office of Nuclear Reactor Regulation is currently reviewing the submittal and has determined that additional information is needed in order to complete the review. The text of the requests for additional information (PAls) and I&M's responses are provided below.

RAI-S BPB-1 Section 3.1 of the license amendment request (LAR) states that "loss of both anticipatory trip channels does not place the plant in an unanalyzed condition and, therefore, the plant should not be required to enter TS [technical specification] Limiting Condition of Operation (LCO) 3.0.3." The LAR does not explain how starting one main feedwater pump causes a loss of both anticipatorytrip channels, nor does it provide the definition of a channel.

a) Clarify the above statement, since starting a main feedwater pump results in a loss of only one anticipatorytrip channel.

b). Explain the concern regardingbeing required to enter TS LCO 3.0.3.

c)-e fine each Engineered Safety Feature Actuation System (ESFAS) Function 6.g channel by identifying associated contacts and relays. Explain whether proposed TS Bases should be clarified regardingthe composition of each channel.

• I&M Response to RAI-SBPB-I:

There is only one anticipaitory trip channel per MEW pump. Section 3.1 of the LAR describes scenarios in which MEW pumps are started and then subsequently undergo a trip for an unknown reason. Because there is only one channel per MFW pump, starting only one MFW pump does not result in the loss of both anticipatory trip channels. It would result in the loss of only one anticipatory trip channel. Also, the discussion of trip channels is based on the premise that normal plant evolutions such as startup and shutdown should not result in entry into an LCO. The trip channels are needed only to mitigate abnormal events...

to AEP-NRC-2016-14 Pg Page 2 a) In the second RAI-SBPB-1 paragraph above, of the the phrase, Summary "loss in Section trip of both anticipatory of the [AR, 3.1 channels" refers referenced in to loss of the channels for a degraded condition, something other than starting a MEW pump. As shown in Figure 1 of Enclosure 2 to Reference 1, in order for the actuation trains for auxiliary feedwater (AFW) pumps to initiate an automatic start, both MEW pump trip channels must be activated.. To clarify the effect that trip channels have on the LCO, Condition H wording "will-be revised to delete the phrase "or more" along with the "(s)" after channel, so that the

... new Condition H will read, "One MEW Pump trip channel inoperable." A markup of the revised TS page is provided in Enclosure 3.

b) Regarding LCO 3.0.3 entry, it has been determined that entry into LCO 3.0.3 would not be required for CNP Unit 2, because there is only one trip channel per pump. With only one trip channel per MEW pump in Unit 2, entry into LCO 3.0.3 for this condition would not be required because each Unit 2 MFW pump is allowed a separate entry into Condition H. In addition, if the loss of both anticipatory trip channels is due to a degraded condition, that should not warrant entry into LCO 3.0.3 because the anticipatory MEW pump trip is not

• credited in the accident analysis.

c) A trip channel is considered to be the position indication switch, which closes when the associated MFW pump steam stop valve closes, along with the relay, as shown in Figure 1 of Enclosure 2 in Reference 1. The RE and Rw relays for the MEW pump trip channels in Unit 2 provide input to the AEW pump actuation train logic as shown in Figure 1 of Enclosure 2 in Reference 1. When the AEW actuation relay for either MFW pump (RE or RW) is energized, a signal is sent to the AFW pump actuation logic circuit. The AEW pumps will not start until signals from both MEW pump channels have been received by the AEW pump actuation logic circuit. Consideration will be given to providing additional clarification in the TS Bases regarding the composition of each channel*.

RAI-SBPB The LAR states that starting a main feedwater pump makes the associatedESFAS Function 6.g channel inoperable until it is supplying feedwater to the steam generators. The LAR proposes adding,n~ew Condition H and Note H. 1. Note H. 1 allows one ESFAS Function 6.g channel on one main feedwater pump to be inoperable for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Proposed Note H. I becomes pertinent,after entering Condition H. The value and purpose of Note H. I is questionable because the proposed Condition H already provides for the channel to be inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The purpose of Condition H is also questionable because Condition B already allows one channel to be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

a) Explain the intended purpose of the proposed TS changes.

b) Explain how the proposed TS changes accomplish the intended purpose. Alternatively, revise .the proposed TS changes.

Enciosure 2 to AEP-NRC-2016-14 Pg Page 3 I&M Response to RAI-SBPB-2:

Proposed Note H.1 states that one MFW pump may be inoperable for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the process of removing the pump from service or placing the pump in service. This provision allows pump startup and shutdown to occur when the MFW pump is reset and not capable of feeding the steam generators, without requiring entry into the Required Action for Condition H.1.

a) This change is being proposed for two reasons. First, as discussed in Reference 1, this change is proposed to provide consistency in format and function between the Unit .1 and Unit 2 TS. Second, as discussed in Section 3.4 of Reference 1, the Note for H.1 is proposed to prevent unnecessary entry into LCO applicability for normal operational occurrences, such as startup and shutdown of a MEW pump.

b) Even though the proposed new Condition H is similar in function to the existing Condition B, the addition of the new Condition H will create consistency with the format of Unit 1 TS, for which this change has already been approved. In addition, the proposed Note to Required Action H.1 will prevent entry into Condition H while placing the MFW system into service or removing it from service, which are evolutions that typically should not require entry into an LCO Condition.

REFERENCES

1. Letter from Q. S. Lies, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Unit 2 License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation," dated October 19, 2015, Agencywide Documents Access and Management System (ADAMS) Accession No. ML15293A497.

Enclosure 3 to AEP-NRC-2016-14, DONALD C. COOK NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATION (TS)

PAGE 3.3.2-3 MARKED TO SHOW PROPOSED CHANGES TS 3.3.2, ESFAS Instrumentation

ESFAS Instrumentation 3.3.2 ACTIONS (continued)___________

CONDITION REQUIRED ACTION COMPLETION TIME El lone Main Feedwatet H.1-----------NOTE-------

IPumP trip channelI One channel on one MFW

[inoperable~l,' pump may be inoperable S for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the process of removing the pump from service or placing the pump in service.

Rsoechannel to 48hoursI HI=]. Required Action and 1*fj.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition B~

not met for Function 6.g.

OR Required Action and associated Completion Time of Condition D not met for Function 6.f.

Cook'Nuclear Plant Unit 2 3323AedetN.2w 3.3.2-3 8