ML051300380

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Report of Changes Pursuant to 10 CFR 50.59 for May 18, 2003 - December 31, 2004
ML051300380
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 05/09/2005
From: Corlett D
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
H N P-05-064
Download: ML051300380 (2)


Text

Progress Energy SERIAL: H N P-05-064 10 CFR 50.59(d)(2)

U. S. Nuclear Regulatory Commission MAY 9

ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT Report of Changes Pursuant to 10 CFR 50.59 DOCKET NO. 50-400/LICENSE NO. NPF-63 Ladies and Gentlemen:

In accordance with 10 CFR 50.59(d)(2), Carolina Power & Light Company (doing business as Progress Energy Carolinas, Inc.) submits the attached report for the Harris Nuclear Plant (HNP).

The report provides a brief description of changes to the facility and a summary of the evaluations required per 1 OCFR50.59 for those items, regardless of implementation status, between May 18,2003 and December 31,2004.

This letter contains no new regulatory commitments. Please contact me if you have any questions regarding this submittal at (91 9) 362-31 37.

Sincerely, D. H. Corlett Supervisor, LicensinglRegulatory Programs Harris Nuclear Plant DHC/rg h C:

Mr. R. A. Musser, NRC Sr. Resident Inspector Mr. C. P. Patel, NRC Project Manager Dr. W. D. Travers, NRC Regional Administrator Progress Energy Carolinas, Inc.

Harris Nuclear Plant P 0 Box165 New Hill, NC, NC 27562

Document Control Desk HNP-05-064/ Attachment 1, Page 1 of 1 10 CFR 50.59(d)(2) Report of Changes, Tests or Experiments Log Number /

Implementing Document EC 55938 04-0601 04-0628 AP-557 (RM-1 FR-3566ASA) 04-1 152 AP-557 (RM-1 FR-RM-1 FR-3564BSB &

3567BSB)

Description of Change During reevaluation of the Safe Shutdown Analysis, HNP identified that control of both Reactor Auxiliary Building (RAB) Electrical Equipment Protection Room ventilation system recirculation dampers could be lost during a postulated fire in certain fire areas. The dampers would fail shut upon loss of power preventing them from allowing recirculation of the air in the room. This modification changed these recirculation dampers failure modes upon loss of power from shut to open. Additionally, circuit changes were made to satisfy the objectives for post-fire safe shutdown contained in General Design Criteria 3, Fire Protection, that are concerned with preventing spurious operation from hot shorts and other affects of thermal and smoke damage.

One detector of one of the Fuel Handling Building (FHB) Area Radiation Monitors (ARM) was out of service for more than thirty-days until maintenance was performed.

Two FHB radiation monitor detectors failed check source testing and the associated FHB radiation monitors were declared inoperable for a period of greater than 30 days until maintenance was performed.

Evaluation Summary There are no safe shutdown conditions that require either of these dampers to be in a position other than open. The modification enhanced safe shutdown capability by eliminating the requirement for local manual actions to open the dampers. In addition, reliability of the system was improved by installing a control switch in the main control room to isolate the control power to one of the dampers to provide an alternate means of opening the damper to prevent spurious operations from hot shorts. This activity does not increase the frequency, likelihood of occurrence or consequences of an accident or a malfunction of an SSC important to safety, does not create a possibility for an accident of a different type or a malfunction with a different result, does not result in a design basis limit being exceeded or altered, and does not depart from a method of evaluation.

The function of this ARM is to generate an isolation signal for the FHB normal ventilation and initiate emergency ventilation in the event of a fuel handling accident. Technical Specifications state that a channel is operable when one or more detectors are operable. This activity does not increase the frequency, likelihood of occurrence or consequences of an accident or a malfunction of an SSC important to safety, does not create a possibility for an accident of a different type or a malfunction with a different result, does not result in a design basis limit being exceeded or altered, and does not depart from a method of evaluation.

The function of these radiation monitors is to generate an isolation signal for the FHB normal ventilation and initiate emergency ventilation in the event of a fuel handling accident. One monitor was inoperable in the FHB North area and one in the South area. Technical Specifications state that a channel is operable when one or more detectors are operable. This activity does not increase the frequency, likelihood of occurrence or consequences of an accident or a malfunction of an SSC important to safety, does not create a possibility for an accident of a different type or a malfunction with a different result, does not result in a design basis limit being exceeded or altered, and does not depart from a method of evaluation.