Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report

Reactor Operation Inconsistent with the Updated Final Safety Analysis Report

ML031210459
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000268, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane
Issue date:	03/18/1996
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
References
IN-96-017, NUDOCS 9603150213
Download: ML031210459 (3)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555-0001

March 18, 1996

NRC INFORMATION NOTICE 96-17:

REACTOR OPERATION INCONSISTENT WITH THE UPDATED

FINAL SAFETY ANALYSIS REPORT

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

The U.S. Nuclear Regulatory Comniission (NRC) is issuing this information

notice to alert addressees to instances of reactor operation that may not

conform to the licensing basis. It is expected that recipients will review

the information for applicability to their facilities and consider actions, as

appropriate, to avoid similar problems. However, suggestions contained in

this information notice are not NRC requirements; therefore, no specific

action or written response is required.

Description of Circumstances

On August 21, 1995, the NRC received a petition under 10 CFR 2.206 which was

supplemented on August 28, 1995, that requested NRC to shut down Millstone

Unit I and take enforcement action based upon alleged violations of licensed

activities related to operation of spent fuel pool cooling systems and

refueling practices.

Followup of the issues raised in the 2.206 petition, including the findings from investigations conducted by the Office of the

Inspector General, found that certain activities at Millstone Unit I may have

been conducted in violation of license requirements and that refueling

activities may not have been conducted consistent with the Updated Final

Safety Analysis Report (UFSAR).

In a letter dated December 13, 1995,

[Accession No 9512150278], NRC subsequently required that the licensee submit

additional information under oath or affirmation pursuant to Section 182a of

the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f). Specifically, the licensee was required to report on actions taken to ensure that future

operation of Millstone Unit 1 will be conducted in accordance with the terms

and conditions of the Millstone Unit 1 operating license, the Commission

regulations, including 10 CFR 50.59, and the Millstone Unit 1 UFSAR.

Discussion

As one element of its response to the letter of December 13, 1995, Northeast

Utilities Service Companies, the licensee for Millstone Unit 1. established an

Event Response Team to determine the causes for inaccuracies contained in the

Millstone Unit 1 UFSAR. A copy of the Executive Summary and of the text of

the resulting licensee report is attached.

The complete document, including

PDR 96031

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IN 96-17 March i8, 1996 attachments, has been placed in the NRC Public Document Room (PDR) in

Washington, D.C. and the local public document rooms (LPDRs) (Accession No.

9603150021).

The Report identifies a number of fundamental factors that led to an

Inaccurate UFSAR for Millstone Unit 1. The Report states that because of the

nature of the causes that the team has identified, the potential exists for

similar configuration management conditions at Haddam Neck and Millstone

Units 2 and 3. As a result, the NRC issued two letters dated March 7, 1996, that are similar to the letter of December 13, 1995.

Because of a number of

operability and design concerns involving Millstone Unit 2, one letter (which

!s attached) required the licensee to submit to the NRC no later than 7 days

before restarting Unit 2 from its current outage the actions taken to ensure

that future operation of Unit 2 will be conducted in accordance with the

license, regulations, and UFSAR. The second letter from NRC requested

Information from the licensee within 30 days regarding actions taken to date

and futire plans to address the conclusions expressed in the 7007 report at

Mill-torqe Unit 3 and Haddam Neck.

This letter is available in the NRC PDR and

the LFias (Accession No. 9603120179).

This informaticn notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

ens M. rutch e

Division of Reactor rogram Management

Office of Nuclear Reactor Regulation

Technical contacts:

Phillip F. McKee, NRR

(301) 415-2040

Internet:pfn.nrc.gov

T. Jerrell Carter, NRR

(301) 415-1153 Internet:tjc~nrc.qov

Attachments:

1. NU Report ACR 7007

2. March 7, 1996, Millstone 2 Letter

3. List of Recently Issued NRC Information Notices

- -

--

-

--

---

-

-

IN 96-17 March 18, 1996 attachments, has been placed in the NRC Public Document Room (PDR) in

Washington, D.C. and the local public document rooms (LPDRs) (Accession No.

9603150021).

The Report identifies a number of fundamental factors that led to an

inaccurate UFSAR for Millstone Unit 1. The Report states that because of the

nature of the causes that the team has identified, the potential exists for

similar configuration management conditions at Haddam Neck and Millstone

Un.ts 2 and 3. As a result, the NRC issued two letters dated March 7, 1996, that are similar to the letter of December 13. 1995.

Because of a number of

operability and design concerns involving Millstone Unit 2, one letter (which

is attached) required the licensee to submit to the NRC no later than 7 days

before restarting Unit 2 from its current outage the actions taken to ensure

that future operation of Unit 2 will be conducted in accordance with the

license, regulations, and UFSAR. The second letter from NRC requested

information from the licensee within 30 days regarding actions taken to date

and future plans to address the conclusions expressed in the 7007 report at

Millstone Unit 3 and Haddam Neck. This letter is available in the NRC PDR and

the LPDRs (Accession No. 9603120179).

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

original siqned by

Dennis M. Crutcfifield, Director

Division of Reactor Program Management

Office of Nuclear Reactor Regulation

Technical contacts:

Phillip F. McKee, NRR

(301) 4;5-2040

Internet:pfm~nrc.gov

T. Jerrell Carter, NRR

(301) 415-1153 Internet:tjcenrc.gov

Attachments:

1. NU Report ACR 7007

2. March 7. 1996, Millstone 2 Letter

3. List of Recently Issued NRC Information Notices

Tech Editor has review. and concurred 3/14/96 DOCUMENT NAME:

96-17.IN

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