W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition

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Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition
ML102300177
Person / Time
Site: Waterford 
Issue date: 08/12/2010
From: Kowalewski J
Entergy Nuclear South, Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2010-0065
Download: ML102300177 (12)
v • d • e


Text

SEntergy Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6660 Fax 504 739 6678 jkowale@entergy.com Joseph A. Kowalewski Vice President, Operations Waterford 3 W3F1-2010-0065 August 12, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition Waterford Steam Electric Station Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

1. W3F1-2010-0019, Technical Specification Table 3.4-1 Isolation Valve Addition, February 22, 2010.
2.

W3F1 -2010-0050, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition, June 8, 2010 [ADAMS Accession Number ML101620417].

3.

NRC Letter, Request for Additional Information Re: Technical Specification Table 3.4-1 Isolation Valve Addition, June 28, 2010.

Dear Sir or Madam:

In letter W3F1-2010-0019 [Reference 1], Entergy Operations, Inc. (Entergy) proposed a change to Waterford Steam Electric Station Unit 3 (Waterford 3) Technical Specifications (TS) Table 3.4-1 Isolation Valve Addition.

During the submittal review process, the Nuclear Regulatory Commission (NRC) determined that a Request for Additional Information (RAI) was required. Letter W3F1-2010-0050 [Reference 2] submitted the additional information. After NRC review of letter W3F1 -2010-0050, additional information was determined to be needed and another RAI [Reference 3] was generated. The response to the RAI is included in the Attachment to this letter.

This letter contains no new commitments.

W3F1-2010-0065 Page 2 If you have any questions or require additional information, please contact William Steelman at 504-739-6685.

I declare under penalty of perjury that the foregoing is true and correct. Executed on August 12, 2010.

Sincerely, JAK/WJS/ssf

Attachment:

Response to-Request for Additional Information

W3F1`-2010-0065 Page 3 cc:

Mr. Elmo E. Collins, Jr.

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001

Attachment to W3FI-2010-0065 Response to Request for Additional Information to W3F 1-2009-0065 Page 1 of 8 NRC REQUEST FOR ADDITIONAL INFORMATION In letter W3F1-2010-0019 [Reference 1], Entergy Operations, Inc. (Entergy) proposed a change to Waterford Steam Electric Station Unit 3 (Waterford 3) Technical Specifications (TS) Table 3.4-1 Isolation Valve Addition. During the submittal review process,' the Nuclear Regulatory Commission (NRC) determined that a Request for Additional Information (RAI) was required. Letter W3F1-2010-0050 [Reference 2]

submitted the additional information. After NRC review of letter W3F1-2010-0050, additional information was determined to be needed and another RAI [Reference 3]

was generated.

The following lists the Waterford 3 NRC RAIs and responses.

RAIl Letter W3F1-2010-0050 RAI 6.b response-We need a summary of the licensee's EQ calculation. All design information has to be completed before we can review the application. The vendor should have these calculations ready.

RAI 1 Response The solenoid valves SI-4052A(RC LOOP 2 SDC SUCTION INSIDE CONTAINMENT BYPASS ISOL) and SI-4052B (RC LOOP 1 SDC SUCTION INSIDE CONTAINMENT BYPASS ISOL) are being purchased from Valcor Nuclear. The Purchase Order (PO) is complete but according to Valcor Nuclear, the qualification reports will not be submitted for approval until late in the fourth quarter 2010 or early in the first quarter 2011.

Letter W3F1-2010-0019 [Reference 1] attachment 4 provided a list of regulatory commitments. Most of the listed commitments were associated with valves SI-4052A(B). The commitments were generated because at the time of the submittal, the SI-4052A(B) PO was not complete and Waterford 3 had not received the vendor design documentation. With respect to the Environmental Qualification (EQ) calculation, Waterford 3 committed that SI-4052A(B) would be procured to comply with the environmental and accident conditions inside containment as shown in Update Final Safety Analysis Report (UFSAR) Table 3.11-1.

Waterford 3 provided the letter W3F1-2010-0019 commitments because of the importance of ensuring the design requirements are met. The changes being proposed to Technical Specification 3.4.5.2 Table 3.4-1 is associated with operational leakage and the EQ requirements do not have explicit applicability to that specification.

The Waterford 3 position is that this portion of the design change can be controlled by the 10CFR50.59 process.

While Waterford 3 agrees that the EQ calculation information is important, we request that the W3F1-2010-0019 commitments provide the necessary assurance that the to W3F1-2009-0065 Page 2 of 8 design change will continue to meet the EQ requirements as confirmed by 10CFR50.59 process review of applicable qualification reports and/or calculations.

RAI 2

Letter W3F1-2010-0050 RAI 7 - The licensee needs to provide a protective coordination curve that shows the penetration, loads, and cables are protected by the fuses/breakers.

RAI 2 Response The solenoid valves SI-4052A and SI-4052B will be powered from Power Distribution Panel (PDP) 3A1-DC circuit 7 (Technical Requirements Manual (TRM) Table 3.8-1 item 18) via electrical penetration #141 and PDP 3B1-DC Circuit 9 (TRM Table 3.8-1 item 50) via electrical penetration #142, respectively. These 125 VDC circuits are protected by two 1OA fuses in series (one each, + and - poles). The attached curve

  1. 27 shows adequate electrical protection for these two circuits.

The indication lights for SI-4052A and SI-4052B are powered from PDP 390A circuit 6 (TRM Table 3.8-1 item 84) via electrical penetration #141 and PDP 391B circuit 6 (TRM Table 3.8-1 item 96) via electrical penetration #142, respectively. These 120 VAC circuits are protected by a 5A circuit breaker and a 10A fuse in series. The attached curve #26 shows adequate electrical protection for these two circuits.

REFERENCES:

1. W3F1-2010-0019, Technical Specification Table 3.4-1 Isolation Valve Addition, February 22, 2010.
2. W3F1-2010-0050, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition, June 8, 2010

[ADAMS Accession Number ML101620417].

3. NRC Letter, Request for Additional Information Re: Technical Specification Table 3.4-1 Isolation Valve Addition, June 28, 2010.

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