Information Notice 1988-47, Slower-than-Expected Rod-drop Times

From kanterella
Jump to navigation Jump to search
Slower-than-Expected Rod-drop Times
ML031150138
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane
Issue date: 07/14/1988
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-88-047, NUDOCS 8807080366
Download: ML031150138 (7)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555

July 14, 1988 NRC INFORMATION NOTICE NO. 88-47: SLOWER-THAN-EXPECTED ROD-DROP TIMES

Addressees

All holders of operating licenses or construction permits for pressurized-water

reactors.

Purpose

This information notice is being provided to alert addressees to a potential

problem regarding slower-than-expected rod drop times.

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 do not constitute NRC require- ments; therefore, no specific action or written response is required.

Description of Circumstances

In a letter dated May 5, 1988, the licensee of Arkansas Nuclear One Unit 2 (ANO-2) informed the NRC that they were unable to meet the Technical Specifi- cation regarding maximum drop time for control rods.

The licensee discovered

the problem as a result of a change in the methodology used for measuring rod- drop times.

The test was part of the startup physics testing after refueling.

The new test methodology requires the interruption of power to the rod drive

mechanisms for all rods simultaneously by means of the reactor trip breakers.

The previous methodology called for the interruption of power to each individu- al drive mechanism. Simultaneous interruption of power to all drive mechanisms

leads to a slower dissipation of stored energy in the holding coils, hence in- creasing the measured rod-drop time.

The new methodology is a more realistic

representation of the safety function.

The licensee found it necessary to

review all of the accident analyses in the Final Safety Analysis Report to

ensure continued conformance with the licensing basis.

Discussion:

The rod-drop test at ANO-2 showed that the maximum drop time was 3.2 seconds, although the Technical Specification required less than 3.0 seconds.

The staff

found that the actions taken by the licensee were acceptable for dealing with

the changes to the safety margins.

The licensee subsequently submitted a reauest

to amend the Technical Specification on an emergency basis. Because problems

similar to that at ANO-4 may occur at other plants, the staff would like to

inform all licensees of this experience so that they may take appropriate

IN 88-47 July 14, 1988 action to avoid requesting amendments on an emergency basis in regard to this

matter. The staff intends to incorporate the lessons learned from the ANO-2 experience in future reviews of accident analyses results, such as reload

reviews.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles 1.

rd1si, D rector

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

N. Prasad Kadambi, NRR

(301) 492-1153 Attachment: List of Recently Issued NRC Information Notices

Attachment

IN 88-47

July 14, 1988 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

88-46

88-45

88-44

88-43

88-42

88-41

88-40

Licensee Report of

Defective Refurbished

Circuit Breakers

Problems In Protective

Relay and Circuit

Breaker Coordination

Mechanical Binding of

Spring Release Device

in Westinghouse Type

DS-416 Circuit Breakers

Solenoid Valve Problems

Circuit Breaker Failures

Due to Loose Charging

Spring Motor Mounting Bolts

Physical Protection

Weaknesses Identified

Through Regulatory Ef- fectiveness Reviews (RERs)

Examiners' Handbook for

Developing Operator

Licensing Examinations

7/8/88

7/7/88

6/24/88

6/23/88

6/23/88

6/22/88

6/22/88

6/15/88

6/15/88

6/14/88

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPk for nuclear

power tractors-.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for BWRs.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

88-39

88-38

LaSalle Unit 2 Loss of

Recirculation Pumps With

Power Oscillation Event

Failure of Undervoltage

Trip Attachment on General

Electric Circuit Breakers

Flow Blockage of Cooling

Water to Safety System

Components

88-37 OL = Operating License

CP = Construction Permit

i

IN 88-47 July 14, 1988 action to avoid requesting amendments on an emergency basis in regard to this

matter. The staff intends to incorporate the lessons learned from the ANO-2 experience in future reviews of accident analyses results, such as reload

reviews.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

N. Prasad Kadambi, NRR

(301) 492-1153 Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES
  • C/OGCB:DOEA:NRR

4CO

psiIK0L- CHBerlinger

Oyj/6-/88

06/28/88

  • SELB:DEST:NRR *SAD/DEST:NRR PPMB:ARM

FRosa

AThadani

TechEd

06/15/88

06/16/88

06/ /88

  • OGCB:DOEA:NRR

NPKadambi

06/28/88

  • SRXB:DEST:NRR

MWHodges

06/15/88

IN 88-XX

June xx, 1988 action to avoid requesting amendments on an emergency basis in regard to this

matter. The staff intends to incorporate the lessons learned from the ANO-2 experience In future reviews of accident analyses results, such as reload

reviews.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

N. Prasad Kadambi, NRR

(301) 492-1153 Attachment:

List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

apic

OGCB:DOEA:NRR

NPKadambi

06)4 /88 D/DOEA:NRR

C/OGCB:DOEA:NRR

CERossi

CHBer) inger

06/ /88

06/04'/88

  • SAD/DEST:NRRŽfPPMB:ARM

AThadani

TechEd

06/16/88

06/d-/88

  • SRXB:DEST:NRR

MWHodges

06/15/88

  • SELB:DEST:NRR

FRosa

06/15/88 D/DLsT: WM

LP

h..

)-. 5lAO

IN 88-XX

June xx, 1988 this matter. It is the intention of the staff to incorporate the lessons

learned from the ANO-2 experience in future reviews of accident analyses

results, such as when conducting reload reviews.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator-of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

N. Prasad Kadambi, NRR

(301) 492-1153 Attachment:

List of Recently Issued NRC Information Notices

OGCB:DOEA:NRR

NPKadambi

06/ /88 SRXB DEST:NRR

MWHodges

06//S-/88 SELB:DEST:NRR

FRosa

06//47/88 D/DOEA:NRR

CERossi

06/ /88A

SAD/DEST:

AThadani I

06/

88 C/OGCB: DOEA:NRR

CHBerlinger

06/ /88 PPMB:ARM

TechEd

06/ /88

IN 88-XX

June xx, 1988 this matter. I1 isr1tnr~hrbeiti

of Xhe stafft

incorporate the lessons

learned from the ANO-2 experience in future reviews of accident analyses

results, such as -wheft-eenductn

breload reviews.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the fegional Administrator of the appropriate regional

office./

Charles E. Rossi, Director

Division of Operational Events Assessment

Office-of Nuclear Reactor Regulation

Technical Contact:

N. Prasad Kadambi, NRR

(301) 492-1153 Attachment:

List of Recently Issued NRC Information Notices

OGCB:DOEA:NRR

NPKadambi

06/

/88 SRXB

T: NRR

MWHodges

06/(Sj/88 SELB:DEST:NRR

FRosa

06//,5/88 D/DOEA:NRR

CERoss

/

06/ /88 SAD/DEST:

ATha4ani

06/(V/88 C/OGCB:DOEA:NRR

CHBerlinger

06/ /88 PPMB:ARM

TechEd 4'WV'J'04

06/St/88