ML20126M761

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Ack Receipt of in Response to Emergency Exercise Weakness Noted in Insp Rept 50-285/92-20.Informs That Item Will Remain Open Until Results of Procedure Evaluations & Changes Committed to in Reviewed
ML20126M761
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/04/1993
From: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Gates W
OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 9301110095
Download: ML20126M761 (5)


See also: IR 05000285/1992020

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NUCLEAR REGULATORY COMMISSION

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Docket No. 50-285

License No. DPR-40

Omaha Public Power District

ATTN:

W. G. Gates, Division Manager

Nuclear Operations

444 South 16th Street Mall

Mail Stop 8E/EP4

Omaha, Nebraska 68102-2247

Gentlemen:

SUBJECT:

NRC INSPECTION REPORT 50-285/92-20

Thank you for your letter dated December 7,1992, in response to the emergency

exercise weakness identified in NRC Inspection Report 50-285/92-20 dated

November 2, 1992. Your response detailed your analysis of the weakness and

identified as a contributing cause the conflicting assessment criteria

contained in your procedures. You also committed to evaluate the conflicting

criteria and initiate procedure changes as necessary.

We have reviewed your response and agree with your analysis that Emergency

Plan Implementing Procedure (EPIP)-OSC-1, Sections 4.0 and Attachment 6.1

appear to permit different interpretations of conditions challenging the

containment fission product barrier. We also agree with your conclusion that

under such conditions, the most conservative assessment and classification

should have been invoked.

This item will remain open until we have reviewed the results of the procedure

evaluations and changes committed to in your response letter.

Should you have any questions concerning this letter, please contact

Dr. D. Blair Spitzberg of my staff at (817) 860-8191.

Sincerely,

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LIJ.jjCallan, Director

Division of Radiation Safety

and Safeguards

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UNITED STATES

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NUCLEAR REGULATORY COMMISSIOM

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Docket No. 50-285

License No. DPR-40

Omaha Public Power District

ATTN:

W. G. Gates, Division Manager

Nuclear Operations

444 South 16th Street Mall

Mail Stop BE/EP4

Omaha, Nebraska 68102-2247

Gentlemen:

SUBJECT: NRC INSPECTION REPORT 50-285/92-20

Thank you for your letter dated December 7,1992, in response to the emergency

exercise weakness identified in NRC Inspection Report 50-285/92-20 dated

November 2, 1992. Your response detailed your analysis of the weakness and

identified as a contributing cause the conflicting assessment criteria

contained in your procedures. You also committed to evaluate the conflicting

criteria and initiate procedure changes as necessary.

We have reviewed your response and agree with your analysis that Emergency

Plan Implementing Procedure (EPIP)-OSC-1, Sections 4.0 and Attachment 6.1-

appear to permit different interpretations of conditions challenging the

containment fission product barrier. We also agree with your conclusion that

under such conditions, the most conservative assessment and clas::ification

should have been invoked.

This item will remain open until we have reviewed the results of the procedure

evaluations and changes committed to in your response letter.

Should you have any questions concerning this letter, please contact

Dr. D. Blair Spitzberg of my staff at (817) 860-8191.

Sincerely,

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L. J. Callan, Director

')ivis on of Radiation Safety

and Safeguards

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Omaha Public Power District

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cc:-

LeBoeuf, Lamb, Leiby & MacRae

ATTN: Harry H. Voigt, Esq.

1875 Connecticut Avenue, NW

Washington, D.C.

20009-5728

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Washington County Board

of Supervisors

ATTN: Jack Jensen, Chairman

Blair, Nebraska 68008

Combustion Engineering, Inc.

ATTN: Charles B. Brinkman, Manager

Washington Nuclear Operations

12300 Twinbrook Parkway, Suite 330

Rockville, Maryland 20852

Nebraska Department of Health

ATTN:

Harold Borchert, Director

Division of Radiological Health

301 Centennial Mall, South

P.O. Box 95007

Lincoln, Nebraska 68509-5007

Fort Calhoun Station

ATTN:

T. L. Patterson, Manager

P.O. Box 399

Fort Calhoun, Nebraska 68023

Program Manager

FEMA Region 7

911 Walnut Street, Room 200

Kansas City, Missouri

64106

Director

Nebraska Civil Defense Agency

1300 Military Road

Lincoln, Nebraska 68508

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J. L. Milhoan

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Spitzberg, DRSS/FIPS

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Section Chief, DRP/TSS

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Resident inspector - Fort Calhoun Station

MIS System

DRSS/flPS File

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Lisa Shea, RM/ALF, (MS MNBB 4503)

S. Bloom, NRR Project Manager (MS 13113)

C. A. Hackney, RSLO

G. F. Sanborn, E0

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December 7, 1992

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LIC-92-337

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U. S. Nuclear Regulatory Comission

ATTN: Document Control Desk

Mail Station PI-137

Washington, DC 20555

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References: 1.

Docket No. 50-285

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2.

Letter from NRC

November 2,1992 (A. B. B,each) to OPPD (W. G. Gates) dated

Gentlemen:

,

SUBJECT:

NRC Inspection Report No. 50-285/92-20, Response to an Identified

Weakness

The subject report transmitted an emergency exercise weakness resulting from an

NRC inspection conducted October 13 through October 16, 1992 at the fort Calhoun

,

Station. Attached is the Omaha Public Power District response to this weakness.

If you should have any questions, please contact me.

Sincerely,

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W. 5 &

W. G. Gates

Vice President

WGG/grc

Attachment

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LeBoeuf, Lamb, Leiby & MacRae

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J. L. Milhoan, NRC Regional Administrator, Region IV

R. P. Mullikin, NRC Senior Resident inspector

S. D. Bloom, NRC Project Manager

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Attachment'

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LIC 92 337

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Page 2

Under the specific safety function for Containment Integrity (6.), the

following acceptance criteria are presented:

Condition 2: Break Inside Containmni

a.

Each Containment penetration not required to be open-has at

least one isolation valve closed. (ERF pages 560-566).

'

b.

Hydrogen concentration < 3.07,or Hydrogen Purge in progress.

c.

Containment Spray flow rate a 2400 gpm total or Containment

pressure s 5 psig.

3.

The

Emergency

Action

Level

(EAL)

in

EPIP-0SC-1,

" Emergency

Classification," which was prompted by an exercise controller was EAL

1.16, which states the following

FAILURE / CHALLENGE TO TWO FISSION PRODUCT BARRIERS

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VERIFICATION CRITERI A:

1.

This event is not covered by any other EAL.

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2.

The event is a failure or challenge to ANY two (2) fission

product barriers listed below (Attachment 6.1).

A.

Fuel Cladding

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B.

Reactor Coolant System

C.

Containment

4.

-Attachment 6.liof EPIP-05C 1, states- the following for Containment:

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C. Containment f ailure or Challenge'

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-Containment Hydrogen Concentration greater than-37..

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2.

Contcinment Pressure greater than 50 psig QB rising at

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a rate that will exceed 60 psig before corrective action

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can halt or reverse the pressure increase.

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Containment ~

Integrity: as- defined-

by--Technical-

Specifications is not ? resent during an unplanned-

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potent 1al exists for loss 'of one 'of

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402/63&2000

December 7, 1992

LIC-92-337

U. S. Nuclear Regulatory Commission

ATTN: Document Control Desk

Mail Station PI-137

Washington, DC 20555

References: 1.

Docket No. 50-285

2.

Letter from NRC

November 2,1992 (A. B. 8,each) to OPPD (W. G. Gates) dated

Gentlemen:

SUBJECT:

NRC Ir.spection Report No. 50-285/92-20, Response to an Identified

Weakness

-

The subject report transmitted an emergency exercise weakness resulting from an

i

NRC inspection conducted October 13 through October 16, 1992 at the fort Calhoun

Station. Attached is the Omaha Public Power District response to this weakness.

If you should have any questions, please contact me.

Sincerely,

1

N. 5 &

W. G. Gates

Vice President

WGG/gre

Attachment

c:

LeBoeuf, Lamb, Leiby & MacRae

J. L. Milhoan. NRC Regional Administrator, Region IV

R. P. Mullikin. NRC Senior Resident Inspector

S. D. Bloom, NRC Project Manager

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Attachment

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LIC 92 337

Page 1

RESPONSE TO AN EMERGENCY EXERCISE WEAKNESS

WEAKNESS

The inspectors noted a problem with emergency detection and classification when

the staf f did not promptly recognize that conditions existed for a Site Area

Emergency classification.

At 9 a.m., the Technical Support Center staff was

aware that containment spray and ventilation coolers were lost and that a primary

coolant leak existed.

These conditions indicated a challenge or loss of the

containment and reactor coolant system fission product barriers as defined in

EPIP-05C-1,

' Emergency Classification'

and,

therefore,

should have been

classified as a Site Area Emergency. At about 9:20 a.m., the Technical Support

Center controller issued a contingency message to the Site Director to declare

a Site Area Emergency.

Failure to promptly classify this event prom)tly in

accordance with the emergency classificaticn procedure was identificc

as an

exercise weakness (285/9220-01).

Response

Omaha Public Power District (OPPD) has completed a review to determine the cause

of the weakness identified during the 1992 NRC Evaluated Exercise on October 16,

1992.

The following information was identified:

1.

EPIP-05C-1, " Emergency Classification," Revision 21, Section 4.0 defines

a Challar.ged Barrier as:

4.1

CHALLENGED BARRIER - A challenge to a barrier is defined as one of

the following conditions:

4.1.1 Inability to maintain a critical safety function which

protects that barrier.

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4.1.2 A situation exists which will cause the failure of the barrier

within a predictable time period unless successful corrective

action occurs.

4.1.3 An event has occurred which has a high probability of having

damaged a fission product barrier, but time has not yet

permitted verification of the failure.

2.

E0P-20 " Functional Recovery Procedure," states the following instructions

under Section 7.0, " Safety function Status Check":

The purpose of this section is to provide a form which enables the

operators to continually verify that the actions they are taking are

adequate to satisfy th; Safety Function Acceptance Criteria.

Satisfying the acceptance criteria assures that the actions beirg

taken are maintaining the plant in a safe condition and also

verifies by independent assessment (performed by the STA) that the

operator has implemented the correct procedure.

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Attachment

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LIC-92-337

Page 2

Under the specific safety function for Containment Integrity (6.), the

following acceptance criteria are presented:

.

Condition 2: Break inside Containment

a.

Each Containment penetration not required to be open has at

[

least one isolation valve closed. (ERF pages S60 566).

b.

Hydrogen concentration < 3.0Y, or Hydrogen Purge in progress.

,

c.

Containment Spray flow rate a 2400 gpm total or Containment

pressure s 5 psig.

3.

The

Emergency

Action

Level

(EAL)

in

EPIP OSC-1,

" Emergency

Classification," which was prompted by an exercise controller was EAL

1.16, which states the following:

-

+

FAILURE / CHALLENGE TO TWO FISSION PRODUCT BARRIERS -

-VERIFICATION CRITERIA:

1.

This event is not covered by any'other EAL.

EM

2.

The event is a failure or challenge to ANY two (2) fission

prcduct barriers listed below (Attachment 6.1).

A.

Fuel' Cladding

B.

Reactor Coolant System

C.

Containment.

4.

Attachment 6.1 of EPIP OSC-1, states the_ following for Containment:

C. Containment Failure or Challenge

1.

Containment Hydrogen Concentration greater than 37..

2.

Containment Pressure greater than 50 psig QB rising at

a rate that will exceed 60 psig before corrective action

can halt or reverse the_ pressure increase.

3.

Containment

Integrity-

as

defined

by

Technical

Specifications is not ? resent during an unplanned

transient AtQ the >otential exists for loss of-one of

- the other two fiss'on product barriers.

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Aftachment

LIC 92 337

Page 3

5.

The FCS Technical Specifications state the following pertaining to

containment integrity:

Containment integrity is defined to exist when all of the following

are met:

(1)

All nonautomatic containment isolation valves which are

not required to be open during accident conditions;and

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blind flanges are closed.

(2)

The equipment hatch is properly closed and sealed.

(3)

At least one door in the personnel air lock is properly-

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closed and sealed.

(4)

All automatic containment isolation valves are operable

er locked closed (or isolated by locked closed valves or

blind flanges as permitted by limiting condition for

operation).

(5)

The

uncontrolled

containment

leakage

satisfies

Specification 3.5.

,

4

The OPPD review identified that by the strict guidance provided in EPIP-0SC-1,.

" Emergency Classification" (item 4, page 2), the plant conditions did not meet

the criteria of a Failure / Challenge to Two Fission Product Barriers.

As a

.

result, an escalation to a Site Area Emergency classification was not required.

However, based upon the definition of a challenged barrier in Section 4.1 of

EPIP-OSC-1, item 4.1.1 (item 1, -page 1), the critical : safety- function for.

Containment was not maintained per the requirements of the Safety Function Status

Checks in E0P-20 (item 2, page 1).

Therefore, this condition could have been

considered to be a challenged barrier.

This condition, along with a known

,

primary to secondary leak, would have satisfied the requirements of t.Al 1.16

(item 3,page2).

OPPD has determined that these conflicting criteria contributed to the weakness,

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and proposes to perform a multi-discipline review of the appropriate procedures..

-

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Corrective Actions and Schedule

.0 PPD will convene a review group to evaluate the conflicting criteria discussed

above,-as well as- other EAL criteria currently in use, 'and initiate procedure

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changes as-necessary.

The group will be composed of personnel from areas that

typically use-the procedures / documents. . Training will be provided to affected

personnel on any changes initiated by the review process. These actions will.be

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