ML110190672

Notice of Forthcoming Meeting with Representatives of Pacific Gas and Electric Company to Discuss Digital Upgrade and Eagle-21 Portion of Reactor Trip System at Diablo Canyon, Units 1 and 2

ML110190672
Person / Time
Site:	Diablo Canyon
Issue date:	01/20/2011
From:	Wang A Plant Licensing Branch IV
To:	Markley M Plant Licensing Branch IV
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME5284, TAC ME5285
Download: ML110190672 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 20, 2011 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation J.

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FROM: Alan B. Wang, Project Manager ()1w' .

Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUB~IECT: FORTHCOMING MEETING WITH REPRESENTATIVES OF PACIFIC GAS AND ELECTRIC COMPANY (TAC NOS. ME5284 AND ME5285)

DATE & TIME: Thursday, February 3, 2011 9:00 a.m. to 4:00 p.m. PST LOCATION: Pacific Gas and Electric Company Energy Center 6588 Ontario Road San Luis Obispo, California PURPOSE: The purpose of the meeting is to discuss the architecture that Pacific Gas and Electric Company (PG&E) will propose to the U.S. Nuclear Regulatory Commission (NRC) for the replacement of the Eagle 21 portion of the Diablo Canyon Power Plant process protection system. This is the third Phase 0 meeting regarding this digital upgrade.

CATEGORY 1:* This is a Category 1 public meeting. The public is invited to observe this meeting and will have one or more opportunities to communicate with the NRC after the business portion, but before the meeting is adjourned.

PARTICIPANTS: Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR).

NRC PG&E J. Polickoski S Patterson J. Reinholdt W. Kemper P. Soenen G. Hough B. Johansen ALTRAN INVENSYS J. Hefler G. Clarkson B. Haynes R. Shaffer E. Quinn S. Zimmerman K. Vu B. Lint S. Sykes

• Commission's Policy Statement on "Enhancing Public Participation in NRC Meetings" (67 FR 36920), May 28, 2002.

M. Markley Westinghouse CS Innovations J. Anderson L. Erin E. Gee N. Norante C. Vitalbo S. Seaman MEETING CONTACTS: Alan B. Wang, NRR James T. Polickoski, NRR 301-415-1445 301-415-5430 alan.wang@nrc.gov james.polickoski@nrc.gov The NRC provides reasonable accommodation to individuals with disabilities where appropriate.

If you need a reasonable accommodation to participate in a meeting, or need a meeting notice or a transcript or other information from a meeting in another format (e.g., Braille, large print),

please notify the NRC's meeting contact. Determinations on requests for reasonable accommodation will be made on a case-by-case basis.

To receive a summary of this meeting and begin receiving other plant-specific e-mail distributions, you must subscribe to the Operating Reactor Correspondence electronic distribution for this plant via http://www.nrc.gov/public-involve/listserver/plants-by-region.html.

Once subscribed, if you wish to discontinue receiving electronic distribution, you may unsubscribe at any time by visiting the same web address above.

Docket Nos. 50-275 and 50-323

Enclosure:

Agenda cc w/encl: Distribution via Listserv

AGENDA FORTHCOMING MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY U.S. NUCLEAR REGULATORY COMMISSION Thursday, February 3,2011 9:00 a.m. - 4:00 p.m. PST

• Introductions

• Interim Staff Guidance (ISG) 6 Update

- NRC Status PG&E Progress ISG 6 Matrix - Vendor and PG&E documents

- Cyber requirements from the NRC perspective

• Project Plan and Schedule

• License Amendment Request (LAR) Discussion Format of LAR - with two vendors, how should the LAR be structured?

LAR submittal as a Tier 1 for Tricon and Tier 3 for CS Innovations Advanced Logic System (ALS) - Potential for update to Tier 1 following ALS Topical approval NRC resources and availability Need for submittal of high-level documents before the LAR for review

• Technical Topics NRC's evaluation of ALS diversity approach - Risks and Challenges Maintenance Workstation Software (non-safety) - Discuss the review the NRC will do and what level of documentation is expected (Software Integrity Level (SIL) 1, etc.)

Time Base Verification - can this be justified without periodic measurement of time base based on how it works (e.g., deterministic worst-case analysis and self-di~gnostics)

Use of simple digital components like isolators, signal conditioners with respect to diversity and common cause failures Diablo Canyon RPS/ESFAS Application Software QA

• Factory Acceptance Test (FAT)

Is an Integrated FAT needed before safety evaluation report (SER)

Is an Integrated Site Acceptance Test (SAT) sufficient after SER

• Questions (NRC Staff)

• Public Comments

• Closing Remarks Enclosure

ML110190672 *via email OFFICE DORLlLPL4/PM DORLlLPL4/PM DORLlLPL4/LA DORLlLPL4/BC DORLlLPL4/PM AWang (BSingal NAME JPolickoski* AWang .IBurkhardt MMarkley for)

DATE 1/19/11 1/19/11 1/19/11 1/20/11 1/20/11

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