ML20149M577

Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Licensee Failed to Assure Electrical Cables Associated W/Sys Necessary to Achieve & Maintain Hot SD Conditions Encl in Fire Barrier

ML20149M577
Person / Time
Site:	Farley
Issue date:	12/04/1996
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20149M566	List: ML20149M564 ML20149M577
References
EA-96-410, NUDOCS 9612170417
Download: ML20149M577 (23)

Text

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l NOTICE OF VIOLATION ,

AND  !

PROPOSED IMPOSITION OF CIVIL PENALTY r Southern Nuclear Operating Company. Inc. Docket Nos. 50-348, 50-364-Farley Nuclear Plant License Nos. NPF-2. NPF-8 t EA 96-410 l

During an NRC inspection conducted during the period September 1 through  !

October 12, 1996. violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedures for NRC  !

l Enforcement Actions." NUREG-1600, the NRC proposes to impose a civil penalty t pursuant to Section 234 of the Atomic Energy Act of 1954, as amended (Act).

l 42'U.S.C. 2282, and 10 CFR 2.205. The particular violations and associated t l civil penalty are set forth below:  :

I l I. Violation Assessed A Civil Penalty I

. t l 10 CFR Part 50. Appendix R.Section III.G.2 requires, in part, where  :

cables or equipment. includin associated non-safety circuits that could  ;

prevent operation or cause ma operation of redundant trains of systems  !

l necessary to achieve and maintain hot shutdown conditions, are located  !'

l within the same fire area outside of containment, the cables and I

equipment and associated non-safr.cy circuits be separated by a fire 1 barrier having a three-hour ratfng, or separated by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards, or one redundant train be enclosed in a fire barrier having a  ;

one-hour rating. i License No. NPF-2. Condition 2.C(4), for Farley Nuclear Plant FNP).

Unit 1. states in part, that Southern Nuclear Operating Company. Inc. '

shall implement and maintain in effect all provisions of the approved >

fire protection program as described in the Final Safety Analysis Report i (FSAR). 6 FSAR. Appendix 9B. Fire Protection Program, documents an evaluation of the FNP fire protection 3rogram as it complies with Appendix R to i 10 CFR 50 and embodies t1e contents of the Fire Protection Program .

Reevaluation as approved by the NRC. Appendix 9B. Attachment B.

10 CFR 50 Appendix R Exemptions, provides the NRC's discussion and ,

evaluation of the licensee's Appendix R exemption requests, and also identifies those systems and components that require one-hour Kaowool ,

fire barriers to meet Appendix R. ,

Contrary to the above the licensee failed to assure that electrical '

cables associated with systems necessary to achieve and maintain hot

, shutdown conditions were enclosed in an one-hour fire barrier as l required by Appendix 9B of the FSAR as evidenced by the following  :

examples:  !

i

1. On October 2, 1996 the NRC identified that the 1B and 1C Safety

- IM ection Pump "B train" power cables in Ro,om 160 of Fire Area i '

j Enclosure 1 i

,' 9612170417 561PO4 i PDR ADOCK 05000348 G PDR

Notice of Violation and Proposed 2 Imposition of Civil Penalty j 1-004 were not fully enclosed by a Kaowool fire barrier (approximately 18 feet of cable tray was unwrapped).

I

2. During the period of October 5-8, 1996, the licensee identified that the IB and 1C Safety Injection Pump "B train" power cables and room cooler cables in Room 175 of Fire Area 1-004 were not fully enclosed by Kaowool fire barriers (approximately 24 inches of cable from four cable trays were unwrapped).

3. During the period of October 5-8, 1996. the licensee also identified that the cables for main steam isolation and auxiliary feedwater flow control in Room 319 of Fire Area 1-042 were not enclosed by an appropriate fire barrier, i .e. , Kaowool . (the entire four foot span of cable tray was unwrapped). (01013)

This is a Severity Level III violation (Supplement I).

Civil Penalty - $50,000 II. Violation Not Assessed A Civil Penalty License No. NPF-2, Condition 2.C(4), and License No. NPF-8, Condition 2.C(6), states, in part, that Southern Nuclear Operating Company, Inc. shall implement and maintain in effect all ]rovisions of the approved fire protection program as described in the :SAR. .

FSAR. Appendix 9B Fire Protection Program, documents the evaluation of the FNP fire protection program against Appendix R to 10 CFR 50 and embodies the contents of the Fire Protection Program Reevaluation as approved by the NRC.

FSAR Appendix 9B, Section 9B.6.1, requires periodic inspections of fire protection systems and equipment to assure acceptable condition of these items. Administrative Procedure. FNP-0-AP-36. Fire Surveillance Procedures and Inspections, Revision 12, required that fire surveillance procedures are performed as written, by qualified personnel, and that these procedures provide the necessary detailed requirements.

Fire Surveillance Procedure. FNP-0-FSP-43. Visual Inspection of Kaowool Wraps, Revision 5. provided the acceptance criteria, instructions, and references to installation details for conducting periodic inspections of Kaowool wraps used to provide the one-hour rated fire barriers prescribed by the Fire Protection Program of FSAR, Appendix 9B.

l Contrary to the above, the licensee failed to implement an adequate l

periodic inspection program for Kaowool one-hour fire barriers in that:

1. The periodic inspections failed to verify that Kaowool fire barriers were being maintained in conformance with installation drawings and the acceptance criteria specified in

Notice of Violation and Proposed 3 Imposition of Civil Penalty l

L Procedure FNP-0-FSP-43. During the period March 4-7, 1996.

l licensee personnel inspected Kaowool wraps in accordance with l

Procedure FNP-0-FSP-43 and did not identify any deficiencies.

However, from July 24 - October 2.1996, the NRC identified multiple examples of installation deficiencies and deteriorating l conditions of Kaowool wraps. Subsecuent inspections by the

! licensee conducted during the perioc October 5-8. 1996, identified I

over a hundred similar installation and degradation problems with existing Kaowool wraps around electrical raceways.

l

2. Personnel Jerforming the periodic inspection required by Procedure NP-0-FSP-43 during March 1996 were not qualified, in that they were not knowledgeable regarding the design.

! installation, or material condition requirements for Kaowool ,

l wraps. These individuals were not adequately trained on Kaowool requirements nor did they have adequate prior experience in installing or inspecting Kaowool.

3. As of October 12. 1996. Procedure FNP-0-FSP-43. Revision 5. did not clearly identify all the critical characteristics to be inspected to assure Kaowool fire barriers were maintained in l conformance with installation drawings (e.g., flammastic fire j

seals and compression). (02014)

. This is a Sever.ity Le. vel IV .violati.on. (Supplement.11. _

Pursuant to the provisions of 10 CFR 2.201. the Southern Nuclear Operating Company. Inc. (Licensee) is hereby required to submit a written statement or explanation to the Director. Office of Enforcement. U.S. Nuclear Regulatory Commission, within 30 days of the date of this Notice of Violation and Pro)osed Imposition of Civil Penalty (Notice). This reply should be clearly marced as a " Reply to a Notice of Violation" and should include for each alleged violation: (1) admission or denial of the alleged violation. (2) the reasons for the violation if admitted, and if denied the reasons why. (3) the l

corrective steps that have been taken and the results achieved. (4) the corrective steps that will be taken to avoid further violations, and (5) the date when full compliance will be achieved. If an adequate reply is not I

received within the time specified in this Notice, an order or a Demand for l Information may be issued as to why the license should not be modified, suspended. or revoked or why such other action as may be proper should not be taken. Consideration may be given to extending the response time for good cause shown. Under the authority of Section 182 of the Act. 42 U.S.C. 2232.

this response shall be submitted under oath or affirmation.

Within the same time as provided for the response required above under 10 CFR 2.201, the Licensee may pay the civil penalty by letter addressed to the Director. Office of Enforcement. U.S. Nuclear Regulatory Commission, with a check, draft, money order or electronic transfer payable to the Treasurer of the United States in the amount of the civil penalty proposed above or may protest imposition of the civil penalty in whole or in part, by a written answer addressed to the Director. Office of Enforcement. U.S. Nuclear i

~. _ . - - - . - - - - - - - - - . - . - - - . _ _ - . - - . _ . .

! Notice of Violation and Proposed 4 Imposition of Civil Penalty t

Regulatory Commission. Should the Licensee fail to answer within the time  !

specified, an order imposing the civil penalty will be issued. Should the j Licensee elect to file an answer in accordance with 10 CFR 2-.205 protesting  !

l the civil penalty, in whole or in part, such answer should be clearly marked -

as an " Answer to a Notice of Violation" and may: (1) deny the violations  ;

listed in this Notice, in whole or in aart. (2) demonstrate extenuating

. circumstances. (3) show error in this iotice, or (4) show other reasons why the penalty should not be imposed. In addition to protesting the civil  ;

l penalty in whole or in part. such answer may request remission or mitigation l of the penalty.

Any written answer in accordance with 10 CFR 2.205 should be set forth  :

separately from the statement or explanation in reply pursuant to '

10 CFR 2.201. but may incorporate parts of the 10 CFR 2.201 reply by specific reference (e.g., citing page and paragraph numbers) to avoid repetition. The attention of the Licensee is directed to the other provisions of 10 CFR 2.205.

L regarding the procedure for imposing a civil penalty. l Upon failure to pay any civil penalty due which subsequently has been I determined in accordance with the applicable provisions of 10 CFR 2.205, this l matter may be referred to the Attorney General, and the penalty unless compromised, remitted, or mitigated. may be collected by civil action pursuant to Section 234c of the Act, 42 U.S.C. 2282c.  !

--. Jhe-response-noted-above-(Reply--to Netice of 4iclation.--letter with payment of- --

civil penalties, and Answer to a Notice of Violation) should be addressed to:

Mr. James Lieberman. Director. Office of Enforcement. U.S. Nuclear Regulatory Commission. One White Flint North.11555 Rockville Pike. Rockville. MD 20852- t 2738. with a copy to the Regional Administrator. U.S. Nuclear Regulatory j Commission. Region II and a copy to the NRC Resident Inspector at the Farley Nuclear Plant.  ;

l Because your res)onse will be placed in the NRC Public Document Room (PDR), to the extent possi ale, it should not include any personal privacy. 3roprietary.

or safeguards information so that it can be placed in the PDR wit 1out  :

redaction. If personal privacy or proprietary information is necessary to  !

l provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a l redacted copy of your response that deletes such information. If you request 1 j withholding of such material, you must s)ecifically identify the portions of l your response that you seek to have withleld and provide in detail the bases i for your claim of withholding (e.g., explain why the disclosure of information l l will create an unwarranted invasion of personal privacy or provide the '

i information required by 10 CFR 2.790(b) to support a request for withholding j confidential commercial or financial information). If safeguards information

{

is necessary to provide an acceptable response, please provide the level of

[ protection described in 10 CFR 73.21.

i l Dated at Atlanta. Georgia j this 4th day of December 1996

=. , _ - . - , -. -, - . - - , - .

' LIST OF PREDECISIONAL ENFORCEMENT CONFERENCE ATTENDEES NOVEMBER 18. 1996 Southern Nuclear Ooeratina Comoany. Inc. (SNC)

J. Woodard. Executive Vice President. SNC D. Morey, Vice President. SNC R. Hill. Plant Manager. Farley Nuclear Plant (FNP)

D. Jones. Engineering Manager. FNP

, J. Thomas, Manager, Engineering Support. FNP J. McGowan, Manager. Safety Assessment and Evaluation Review L. Bailey, Project Engineer, SNC J. Love. Bechtel Nuclear Reculatory Commission L. Reyes. Deputy Regional Administrator. Region II (RII) l E. Merschoff. Director. Division of Reactor Projects (DRP). RII l J. Jaudon, Deputy Director. Division of Reactor Safety (DRS), RII C. Evans. Regional Counsel l

B. Uryc. Director. Enforcement and Investigations Coordination Staff (EICS),

RII H. Berkow. Director, Projects Directorate II-2, Office of Nuclear Reactor l

Regulation (NRR) ' ' ' ' '

._ -...p.; . . Ski nner:~Chtef-"' Branch 2~ T'DRP'." Ril" D. Verrelli. Acting Chief. Special Inspection Branch. DRS. RII T. Ross, Senior Resident Inspector. FNP R. Caldwell, Resident Inspector . FNP R. Wright. Project Engineer, DRP. RII R. Carroll. Project Engineer. DRP. RII W. Miller. Reactor Inspector. DRS, RII A. Boland. Enforcement Specialist. EICS. RII E. Connell, Fire Protection Engineer Plant Systems Branch, NRR*

I l

1

• Participated by Telephone Enclosure 2

. - -- - - .. - - . - = _ - -

i

^5 LICENSEE COMMENTS ON INSPECTION REPORT NOS. 50-348. 364/96-09

1. Typographical Error: The date " September 3" referenced on Page 30 in the first and second paragraphs of Section F2.1.b is incorrect. The date should read " September 5."

2. Typographical Error: The cable tray designation "BFDD15" referenced on the last line of the last paragraph on Page 32 is incorrect. It should read "BFDB15".

3. Clarification: The last sentence of the first paragraph of Section F2.1.b on Page 30 states that the licensee "did not consider conducting their own inspections . . . ." During the November 18. 1996, predecisional enforcement conference. the licensee stated that, in response to NRC concerns, on September 5, 1996, they had conducted an inspection of all motor-operated valve cables / conduits required to be wrap]ed with Kaowool for 10 CFR 50 Appendix R. This was the first time the 4RC became aware of this particular licensee inspection effort.

4. Clarification: Item 5 of Section F2.1.b on Page 33 states that over a hundred instances were identified during the licensee's augmented inspection where the Kaowool fire barriers were not properly sealed with flammastic per Procedure FNP-0-PMP-507. "Kaowool Installation -

Procedure." During the November 18. 1996, predecisional enforcement ~

76fifdferids','"t'he licensee ~s'ta'ted ~thht~ the' KaoW661 fire ba~rrier wraps in

~

question were originally installed per Drawing No. A-177541, several years before Procedure FNP-0-PMP-507 was initially issued. The NRC acknowledges this distinction: however. Procedure FNP-0-PMP-507 was identified in the inspection report because it was a source of installation criteria used by inspectors during the licensee's augmented inspection of October 4-8, 1996. It should be noted that the design criteria of Procedure FNP-0-PMP-507 were consistent with Drawing No. A-177541.

5. Clarification: The fifth paragraph of Section F2.1.b was not clear in that the inspections prescribed by Procedure FNP-0-FSP-43 were periodic inspections rather than independent inspections to verify installation.

Consequently, the qualification of inspectors for periodic inspections (i .e. , Procedure FNP-0-FSP-43) is required by Procedure FNP-0-AP-36, and qualification of inspectors for independent inspections is required by l Section 98.6.1.E of the Fire Protection Program.

1

6. Clarification: The discussion in the second to last paragraph of l Section F2.1.b was not clear in that Section 98.6.1 of the Fire  ;

Protection Program requires both periodic and independent inspections, i of which Procedure FNP-0-FSP-43 is the periodic inspection procedure. l Enclosure 3 l

l l

PREDECISIONAL ENFORCEMENT CONFERENCE AGENDA FARLEY NOVEMBER 18,1996, AT 10:30 A.M.

NRC REGION ll OFFICE, ATLANTA, GEORGIA I. OPENING REMARKS AND INTRODUCTIONS Luis A. Reyes, Deputy Regional Administrator s

ll. NRC ENFORCEMENT POLICY

>- B. Uryc, Director 1

Enforcement and Investigation Coordination Staff Ill.

SUMMARY

OF THE ISSUES

< E. Merschoff, Director Division of Reactor Projects (DRP)

IV. STATEMENT OF CONCERNS / APPARENT VIOLATIONS E. Merschoff, Director ~ ~

- ~ Divisio'ri of Reactor Project's (DRP)

V. LICENSEE PRESENTATICN D. Morey, Vice President - Introduction D. Jones, Manager of Engineering - Design issues R. Hill, Farley General Manager - Field installations J. Thomas, Engineering Support Manager - Inspection

& Where Utility is Proceding 1 D. Morey, Vice President - Conclusion VI. BREAK / NRC CAUCUS Vll. NRC FOLLOWUP QUESTIONS Vill. CLOSING REMARKS Luis A. Reyes, Deputy Regional Administrator j l

l Enclosure 4

ISSUE TO BE DISCUSSED ,

1. Final Safety Analysis Report (FSAR), Appendix 9, Fire Protection ,

Program (FPP), implemented by License Condition 2.C.(4) for Unit 1, documents the evaluation of the FPP against Appendix R to 10 CFR 50 and identifies the cables and raceways that require a 1-hour fire barrier to meet Appendix R. Appendix R, Ill.G.2 requires, in part, where cables or equipment that could prevent operation or cause maloperation of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located within the same fire area outside of containment, that the -

cables and equipment and associated non-safety circuits are . ,

separated by a fire barrier having a 3-hour rating, or separated by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards, or one redundant train is enclosed in a fire barrier having a 1-hour rating.

O The NRC identified on October 2,1996, that the IB (swing

. . pump) and.lC. Char.ging... Pump _ B train, power cables in Room 160 were not fully enclosed in a fire barrier having a 1-hour rating.

9 The licensee identified, during the period October 5-8, 1996, that the 18 and 1C Charging Pump (B train) power cable and room cooler cables were not fully enclosed in a fire barrier having a 1-hour rating.

9 The licensee identified, during the period October 5-8, 1996, that the cables for main steam isolation and auxiliary feedwater flow control were not wrapped at all by a fire barrier having a 1-hour rating.

NOTE: Apparent violations discussed in this predecisional enforcement conference are subject to further review and subject to change prior to any resulting enforcement decision.

j .

2. FSAR, Appendix 9B, Fire Protection Program, License No. NPF-2, Condition 2.C(4), and License No. NPF-8, Condition 2.C(6),

4 documents the evaluation of the FNP fire protection program i against Appendix R to 10 CFR 50 and embodies the contents of

) the Fire Protection Program Reevaluation as approved by the NRC.

! FPP, Section 9B.6.1, requires an independent and periodic inspection program to verify fire protection systems conform with installation drawings and test procedures, and are maintained in  ;

an acceptable condition.

l Fire Surveillance Procedure, FNP-0-FSP-43, Visual inspection of i Kaowool Wraps, Revision 5, provided the acceptance criteria, ,

i instructions, and references of installation details for conducting j periodic inspections of Kaowool wraps used to provide the 1-hour

[ rated fire barriers prescribed by the Fire Protection Program of i UFSAR, Appendix 9B.

l 9 The. licensee's periodic and. independent insp.ection program l

' ~

failed to verify that Kaowool fire barriers were installed and maintained in conformance with installation drawings. (During the period March 4-7,1996, licensee personnel inspected the  ;

Kaowool wraps in accordance with FNP-0-FSP-43 and did not identify any deficiencies. However, from July 24 - October 2, 1996, the NRC identified numerous installation and material '

condition deficiencies.)

S Licensee inspections conducted October 5- 8,1996, l identified numerous Kaowool wrap deficiencies. 1 9 Personnel performing periodic Kaowool inspections were not knowledgeable and or trained in the installation and design requirements.

9 Instructions for periodic inspections failed to provide adequate acceptanc'e criteria for compression of Kaowool or all critical characteristics to be inspected.

NOTE: Apparent violations discussed in this predecisional enforcement conference are subject to further review and subject to change prior to any resulting enforcement decision.

Kaowool at Farley Nuclear Plant

+ Mastic Sealant is not Critical for Adequate Fire

Protection

+ Confident in our As Built Drawings l

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+ Confident in our l 1 Configuration Management 1

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'Y N MOTE' SEE SHEET * 'l FOR 40TES 4 LEGEMD 3 _AN @ 39'- O "

4 gECNKL COIF. Joe 7587 03 SOUTHERN SE3MCES INC.

. hec.l . ALA?tMA POWER COMPANY

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FNP Tray & Conduit, Details and Notes A 177541 sh.18J Step 5.8 t

l Rev/ Purpose of Date Text of Change Change 0 "In areas such as floors, To give direction for 04-17-80 installing a fire protection walls, ceilings where seai around cabie trays the blanket wrap ends, when they penetrate floor, walls and ceiling.

fire protect. ion seals shall be installed using -

mastic coatings as specified.

The sealant shall be trowel or sprayed completely around the wrapped cable tray at the floor, walls or ceiling. The seals shall be not less than 1/4" thick and extend not less than 8" onto the l Kaowool wrap, not-less than 8"  ;

l onto the floor, wall or ceiling."

l j

L:'whdhj-1196. doc

_---_----__-_________-___-_-_1

9 Appendix R 1981 -

1985

. Extension reviews e Inspections, as necessary  !

= No significant discrepancies

. No indications for complete inspections

i t

I

. SEQUENCE OF EVENTS FOR KAOWOOL CONCERNS  ::

i

. 2 SEPARATE INSPECTION PROGRAMS I

i I

i I

i h

f I

SEQUENCE OF EVENTS e JULY / AUGUST - NRC IDENTIFIED MOV DISCREPANCIES 9/5/96 NRC EXIT - SCOPE: MOV TERMINATIONS l

• 9/5/96 FNP WALKDOWN OF APPX. R REQ'D MOV'S l 9/11/96 SCOPE CHANGE TO QUESTIONS ON MASTIC l 10/2/96 SCOPE CHAi4GE-TO UNWRAPPED RACEWAYS

l 1

1 TWO (2) SEPARATE INSPECTION PROGRAMS l

l l

. ORIGINAL INSTALLATION - CONST QC TO VERIFY PER DESIGN

. PERIODIC FSP TO IDENTIFY REQUIRED CORRECTIVE MAINT

FNP-0-r37 ,

VISUAL INSPECTICN Cr TJCWOCL WRAPS 1.0 Purcose To inspect the fire protection kamal wraps.

2.0 Accectance criteria Knowool wraps are free fecra physical damage.

3.0 Initial conditions None 3.0 Precautions and Limitations Notify Shif t foreman if damaged knowool is found.

5.0 Insensctiens 5.1 visually inspect the Kaowool wraps in end of the rooms listed on the Table to ensure no physical damage exists (i.e no tears in the cuter wrap or damaged Intermastic or riammaastic around hangers and penetrations).

5.2 If a damaged wrap is discovered notify the Shif t foreman so that an LCO can be initiated.

5.3 Subnit a tER to repair deficiencies.

5.4 Initial checklist upon completion of each room.

tort: During this inspection if any damaged marinite board is observed, subnit an fMR to have it repaired, however no shift roreman notification is required.

6.0  ?.eferences rsAn volu:ne 17 1 I

1 1 Rev. O i

! ....t-OVHD 1

PHP-0-FSP-43 TABLE II INSPEL w eU 0 COL WRAP to. LOCATIO1/DESCRIPTICII (INITIAL) LOCATIOf DRANI?GS D-203248,D-203249 2117 Vertical Cable Chase - 100' Unit II 2159 R.E. reed Pu=o Room - 100' Unit II - RCA l D-203281 2160 East Ha11vay - 100' unit II - RCA l D-203281 D-203267,D-203281 2161 Corridor - 100' Unit II - RCA 2162 Corridor - 100' Unit II - RCA D-203267

,D-203267 2163 WDs Centrol Panel - 100' Unit II - RCA 2168 CM Pu=0 Room - 100' Unit II - RCA l D-203267 2172 Charcine Pu=o Hallvav - 100' Unit II - RCA D-203281 2175 East Hallway - 100' Unit II - RCA l D-203281

' 2182 Storace Poom - 100' Unit II - RCA l l D-203281 l l D-203262,0-203266 N 2185 CCW Rx Room - 100' Unit II Boric Acid Area - 100' Unit II - RCA l l D-203272 v 2186

,2189 Plant Heat. Ecuio. Roce - 100' Unit ,II l l D-203265 Sht.1

2190 AEW Control Panel Poem - 100' Unit II l l D-203265 Sht. 1 l l D-203259,D-203285,D-2032 2209 Hallvav - 121' Unit II - RCA l D-203246,D-203285 I ^~0 Hallvav - 121' Unit II

& nil Corridor - 121' Unit II lD-203284 Picino Penetratien Room - 121' Unit II - RCA D-203245

__2223 2244 Battery Room Mezzanine - 121' Unit II D-203284 v

~

2245 Batterv Room Mezzanine - 121' Unit II D-203285 N 2300 l D-203269,D-203270 West Cable Chase - 139' Unit II 2312 Hallvav - 139' Unit II - RCA l lD-203275 2316 Hallway - 139' Unit II - RCA D-203275 D-203209,D-203279 2319 Hallvav - 139' Unit II 2322 Hallway - 139' Unit II - RCA __

D-203275 2452 Clean Storace Area - 155' Unit II D-203215 2462 Non-Rad Vent. Ecuio. P.oca - 155' Unit II D-203214 2466 West Cable Chase - 155' Unit II D-203269 2500 West cable Chase - 168' Unit II D-203269 2-502 No. 2 Stairvay - Unit II D-203274 2201 Comcuter Room - 121' Unit II D-203246 O

Rev. 2

!?P/ PSP-2/4 4 O V H O 2.

- FNP-0-FSP-43 FARLEY NUCLEAR PLANT UNIT I & 2  !

FIRE SURVEILLANCE PROCEDURE VISUAL INSPECTION OF KAOWOOL WRAPS 1.0 Purcose To inspect the fire protection Kaowool wraps.

2.0 Acceetance Criteria Kaowool wraps designated by an "R" require at least a 2" thick Kaowool wrap to function properly as a fire barrier. Kaowool wraps designated by an "H" require at least a 1" thick Knowool wrap to function properly as a fire barrier. There should be no gaps, cuts, breaks or damage such that Kaowoolis missing.

3.0 Initial Conditions 3.1 Obtain proper release ofwork authorization.

4.0 Precautions and Limitations Notify Shift Foreman if damaged Kaowool is found.

5.0 Maintenance Instructions 5.1 Visually inspect the Kaowool wraps using the referenced drawings for each of the rooms listed on Tables 1 and 2 to ensure no physical damage exits.

5.2 If a Kaowool wrap is dete:Tnined to be inoperable, notify the Shift Supervisor so that a administrative LCO can be established. Damage to the Zetex (outer wrap) does not render the barrier inoperable, however a Deficiency Report (DR) should be submitted to correct the deficiency. Fire watch requirements will be determined in accordance with FNP-0-SOP-0.4.

t 5.3 Submit a DR to repair deficiencies.

I 5.4 Initial checklist upon completion of each room.

NOTE: During this inspection if any damaged marinite board is observed, submit a DR l to have it repaired, however no Shift Foreman notification is required.

5.5 For a partial inspection, fill in the required information in the spaces provided on Table 3.

l Revision 5 l

N t/b.!li 3