ML20196H628
| ML20196H628 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/04/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196H625 | List: |
| References | |
| NUDOCS 8803110169 | |
| Download: ML20196H628 (3) | |
Text
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casog jo, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655
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,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR RFACTOR REGULATION SUPPORTING AMENDMENT NO. 31 TO FACILITY OPERATING LICENSE NO. NPF-38 LOUISIANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By application dated December 11, 1987, as supplemented by letter dated December 22, 1987, Louisiana Power and Light Corpany (LP&L or the itcensee) requested changes to Facility Operating License No. NPE-38 for Waterford Steam Electric Station, Unit 3 (Paterford 3). The proposed changes would revise Technical Specification Limiting Condition for Operation (LCO) 3.3.3.8 and its associated Table 3.3-11 to implement a proposed change in method of fire detection for the annulus wherein the current system will be repinced with fire detection instruments mounted on the Annulus Negative Pressur? System (ANPS)ductwork.
2.0 DISCUSSION The licensee has proposed to change the method of fire detection for the annulus area, citing the desire for a more accessible and improved detection system as the primary reason for replacing the existing system.
The licensee has met with the staff to discuss this change, and has documentation describing the proposed system and demonstrated that the changes will not reduce the level of fire protection at Waterford 3.
The existing annulus fire detection system consists of 69 ionization type smoke detectors circling the annulus in three loops at elevations -4,
+?l, and +46.
These three loops comprise two zones of detection for alarm purposes. The proposed fire detection system consists of two photoelectric smoke detectors rounted on the ANPS duckwork with sample tubes penetratirg into the duct. The ANPS operates continuously during normal plant operation to maintain the annulus negative pressure greater than five inches water gauge in accordance with TS 3.6.6.2.
1 Table 3.3-11 lists fire detection instrunerts, by function and location, which are subject to the LCO and Survaillance Requiremants of Technical Specification 3/4.3.3.8. The proposed changes to Table 3.3-11 consists of reducina the number of Function A detection instruments from 69 to two, the number of zones from two to one; and indicating detectinn at elevation +46 only.
Futber, a footnote will be added to the table to t
clarify that the fire detection instruments for the annulus are physically 8803110169 880304 PDR ADOCK 050003B2 p
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installed on the ANPS doctwork in the P,AB. The change to Statement c of TS 3.3.3.8 does not change the intent of the statement, but rather modifies the language to be consistent with the proposed system confic,uration. As a result of r.oving the detection irr.truments to a location cutside the annulus, the surveillance interve.1 requirements of TS 4.?.3.8.1 and 4.3.3.8.2 will change from "each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless perfomed in the previous 6 months" to "at least once per 6 renths".
However, this occurs within the context of the existing surveillarce requirement lancuage.
3.0 EVALUATION The proposed Technical Specification changes will implement a proposed charge in the arrulus fire detection systen. The staff reviewed information provided by the licensee relative to the fire detection system change as part of its evaluation of the proposed Technical Specification change.
The information which has bea.n provided indicates that renditions in the annulus provide littic opportunity for a fira to occur. Thase unfaverable corditions include: minimal combustible loading; an absence of ionition sources; low oxygen concentration; and strict control of transient combus-tibles and access to the annulus. The licensee has verified operability of the proposed system by perfoming a field test of a nock-up which closely approxinates the proposed systen design. An added c.msure of assuracco that the proposed modification will provida appropriate protec-tien for the atterdant hazards is found in the fact that penetratiens traversing the annulus are located below and in the same relative vicinity of the annulus as the intake duct of the ANPS. Thus, combustion byproducts originating at or near the penetratiers are expected to be rapidly pulled into the AFPS intake duct and quickly sensed by the smoke detectors mounted tharcin.
In addition, the preposed changes will ircrease system reliablity through the elimination er significant reduction in spurious alanns, and the accessiblity of detection instrumerts for raintanance activities and surveillance testing, thus reducing rarsonnel exposure.
The staff concludes that the proposed changes to Technical Specification LCO 3.3.3.8 and its asscciated Table 3.3-11, result in an acceptable lael of fire protection, are consistent with the provisions of Branch Technical Position CMEB 9.5-1, and are, therefore, acceptable.
4.0 C0FTACT WITH STATE OFFICIAL The NRC staff has pdvised the Administrater, Nuclear Energy Division, Offica of Environmental Affairs, State of Louisiana of the proposed datermination of no significant hazards consideration. No corrents were received.
5.0 ENVIRONMENTAL CONSIDEP.ATION The amendment relates to changes in irstallation or use of a facility component located within the restricted area as dafired in 10 CFR Part 20.
The staff has determined that the amendment involves ne significant increase ir the amounts and no significant charge in the types of any effluents that may be released offsite and that there is no sienificant
increase in individual or cumulative occapational radiation exposure. The Commission has previously issued a proposed finding that this amendrent involves no significant hazards consideration ard there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no anvironmental impact statenent or environ-mental assessrent need be prepared in connection with the istuance of this amendment.
6.0 CONCLUSION
Based upon its evaluatien of the proposed changes to the Waterford 3 Technical Specifications, the staff has concluded that:
there is reason-able assurance that the haalth and safety of the public will not be endangered by cperation in the proposed marner, and such activitier will be cerducted in compliance with the Commission's ranulatiers and the issuance of the amendment will not be inimical to the comron defense and security or to the health ar.d safety of the public. The staff, therefore, concludes that the proposed changes are acceptable, and are hereby incorperated into the Waterford 3 Technical Specifications.
Dated: March 4,1E88 Principal Contributor:
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March 4, 1988 Docket No. 50-382 Mr. J. G. Dewease Senior Vice President - Nuclear Operations Louisiana Power and Light Company 317 Baronne Street, Mail Unit 17 New Orleans, Louisiana 70112
Dear Mr. Dewease:
SUBJECT:
ISSUANCE OF AMENDMENT NO. 31TO FACILITY OPERATING LICENSE NPF WATERFORD STEAM ELECTRIC STATION, UNIT 3 (TAC NO. 66792)
The Commission has issued the enclosed Amendment No. 31 to Facility Operating License No. NPF-38 for the Waterford Stwam F,lectric Station, Unit 3.
The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 11, 1987, as supplemented by letter dated December 22, 1987.
The amendment changes the Appendix A Technical Specifications by changing the method of fire detection in the containment annulus.
A copy of the Safety Evaluation supporting the amendment is also enclosed.
Notice of Issuance will be included in the Commission's next Bi-weekly Federal Register notice.
Sincerely, N
David L. P g nton, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects O'fice of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 3I to NPF-38 2.
Safety Evaluation cc w/ enclosures:
See next page e r-c,
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Mr. Jerrold G. Dewease Waterford 3 Louisiana Power & Light Company cc:
W. Malcolm Stevenson, Esq.
Regional Administrator, Region IV Monroe & Leman U.S. Nuclear Regulatory Commission 1432 Whitney Building Office of Executive Director for New Orleans, Louisiana 70103 Operations 611 Ryan Plaza Drive, Suite 1000 Mr. E. Blake Arlington, Texas 76011 1
Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW Mr. William H, Spell, Administrator Washington, D.C.
20037 Nuclear Energy Division Office of Environmental Affairs Resident Inspector /Waterford NPS Post Office Box 14690 Post Office Box 822 Baton Rouge, Louisiana 70898 4
K111ona, Louisiana 70066 i
Mr. Ralph T. Lally President, Police Jury Manager of Quality Assurance St. Charles Parish Middle South Services, Inc.
Hahnville, Louisiana 70057 Post Office Box 61000 New Orleans, Louisiana 70161
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Chairman Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge, Louisiana 70825-1697 Mr. K. W. Cook Nuclear Safety and Regulatory Affairs Manager Louisiana Power & Light Company 317 Baronne Street New Orleans, Louisiana 70112 4
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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
s A.
The application for amendment by Louisiana Power and Light Company (the licensee) dated Deceniber 11, 1987, as supplemented December 22, 1987, complies with the standards and requirements of 3
the Atomic Energy Act of 1954, as amended (the Act), and the 1
Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized l
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 31, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMnISSION 4. CA+
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4, IR88 l
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e ATTACHMENT TO LICENSE APEPPPENT NO. 31 TO FACILITY CPERATING LICENSE N0. NPF-38 DOCKET NO. 50-382 Peplace the following pager of the Appendix A Teebnical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 3-49 3/4 3-49 i
3/4 3-52 3/4 3-52*
3/4 3-53 3/4 3-53 i
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- Anendment Nurber was inadvertently marked out when issued es an overleaf page to Arendment No. 74 Page reissued correctly.
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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detec-tion zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
With any, but not more than one-half the total in any fire zone a.
Function A fire detection instruments shown in Table 3.3-11 inoperable except for the annulus, restore the inoperable instrument (s) to OPER-l ABLE status within 14 days or within tha next I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
b.
With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable except for the l
annulus, or with any Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detec-tion instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoper-able instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor air temperature at least once per hour at the locations listed in Specification 4.6.1.5.
With both annulus detection instruments inoperable, restore at least c.
1 detector to operable status or within the next I hour establish a fire watch patrol to inspect the zone at least once per eight hours.*
d.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUT 00WN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
4.3.3.8.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months.
Circuits which are not accessible during plant opera-tion shall be demonstrated OPERABLE during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.
- Fire watch patrol may be temporarily suspended during performance of Specification 4.6.6.1.a.
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WATERFORD - UNIT 3 3/4 3-49 AMEN 0 MENT NO. 15, 31 i
_ INSTRUMENTATION FIRE DETECTION INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) 4.3.3.8.3 The nonsupervised circuits associated with detector alarms between the instrument and the control room shall be demonstrated OPERABLE at least once per 31 days, 4.3.3.8.4 Each of the resistor wires required by Table 3.3-11 shall be demonstrated OPERABLE at least once per 6 months by verifying the proper wire resistance.
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WATERFORD - UNIT 3 3/4 3 50 1
TABLE 3.3-11 FIRE DETECTION INSTRUMENTS TOTAL NUMBER OF INSTRUMENTS
- ELEVATION HEAT FLAME SMOKE ZONE ROOM NAME/ NUMBER (ft)
M@@
1.
REACTOR AUXILIARY BUILDING RAB 1A Main Control Panels 1,2,3,4,6,7,8,35,36 +46 10/0 RAB 1A Control Room Proper /304
+46 20/0 RAB 1B Emergency Equip. H&V Room /314
+46 0/12 RAB 10 Computer Room (above raised floor)/306 +46 5/0 Computer Room (below raised floor)/306 +46 0/7 RAB 2 Ventilation Equip. Room /299
+46 0/36 RAB 3 RAB Corridor to Relay Room /261
+35 0/1(3) 4/0 RAB HVAC Switchgear Equip. Room /323
+46 0/10 RAB 3A RAB Battery Exhaust Fan Room /406
+69 0/2 RAB 4 Cable Vault /260
+35 0/27 RAB 5 Electrical Penetration Area "A"/263
+35 0/13 RAB 6 Electrical Penetration Area "B"/263A
+35 0/14 RAB 7 Relay Room /262
+35 (3) 12/0 Isolation Panels (9 Compartments
+35 2/0
- 2 per comp.)
RAB 8A High Voltage Switchgear Room "A"/212A
+21 0/1(1) 18/0 RAB 8B Electrical Equip. Room /225B and High
+21 0/1(2) 28/0 Voltage Switchgear Room "B"/212 480V Switchgear 3A32 Room
+21 (2) 2/0 RAB 8C High Voltage Switchgear Room
+21 (1) 8/0 "A-B"/212B RAB BE CEA M/G Set Room /216
+21 2/0 RAB 9 Remote Shutdown Panel Room /217
+21 1/0 RAB 11 Battery Room "B"/213
+21 2/0 RAB 12 Battery Room "AB"/214A
+21 2/0 RAB 13 Battery Room "A"/214
+21 2/0 RAB 15 Emergency Olesel Gen. "B" Room /222
+21 0/1 RAB 15A Emergency Diesel Gen. "B" Feed TK
+46 0/1 Room /328A RAB 16 Emergency Diesel Gen. "A" Room /221
+21 0/1 RAB 16A Emergency Diesel Gen. "A" Feed Tk.
+46 0/1 Room 328A RAB 17 CCW Heat Exchanger "B"/236
+21 0/4 RAB 18 CCW Heat Exchanger "A"/220
+21 0/4 RAB 19 CCW Pump "A"/235
+21 0/2 l
+21 0/2 RAB 21 CCW Pump "B"/233
+21 1/0 RAB 23 Corridor to CCW Pumps /218, Corridor
+21 0/39 to CCW Heat Exchangers/219 and Corridor to Emergency Olesel Gen./225A (1) Common Resistor Wire (2) Common Resistor Wire (3) Common Resistor Wire WATERFORD - UNIT 3 3/4 3-51 AMEN 0 MENT NO. 25, 24
3 VABLE 3. 311 (Continued)
FIRE DETECTION INSTRUMENTS TOTAL NbMBER CF INSTRUMENT 5*
ELEVATION HEAT FLAME SHOKE ZONE ROOM NAME/ NUMBER (ft)
MMd 1.
REACTOR AUXILIARY BUILDING (Continued)
RAB 25 Equip. Access Area /226 (wing area)
+21 15/0 RAB 27A H&V Room /124
+7 0/6 RAB 27B Electrical Area and Health Physics
+7 0/35 Offices /122 RAB 27C I&C Room /120
+7 0/6 l
RAB 270 Communications Equip. Room /123
+7 1/0 RAB 31 Corridors and Passageways
-4 0/24 Corridors on eastside
-4 0/21 RAB 32 Wing Area westside - Auxiliary Com-
-35
'32/0 ponent Cooling Water Pump "A"/853 and Pipe Penetration Area /8100
-4 Wing Area Center /853 and 8100
-35 &
28/0
-4 Wing Area eastside-Component Cooling
-35 31/0 Water Pump "B"/853 and Pipe Penetration Area /8100
-4 RAB 33 S/0 Cooling Heat Exchangers A&B/820
-35 0/1B
& 848 RAB 34 Valve Operating Enclosure Bay Room
-15.5 2/0 "A"/854 Valve Operating Enclosure Bay Room
-15.5 4/0 "B" B55A RAB 35 Safety Injection Pump Room B/816
-35 10/0 RAB 36 Safety Injection Pump Room A/ BIS
-35 10/0 RAB 37 Motor-Driven Emergency Feedpump
-35 0/1 "A"/B49A RAB 38 Motor-Driven Emergency Feedpump
-35 1/0 "B"/B49B RAB 39 General Equipment Area /85,12,13
-35 0/10
& 49 Corridors & General Equip. Areas /B5,
-35 0/28 1, 2, 3, 4, 39, 40, 41, 42, 44 & 46 East Corridor & General Equip. Areas /
-35 0/15 817, 23 & 25 BA Make-up Tank "A"/838
-35 4/0 BA Make-up Tank "B"/B53A
-35 4/0 RAB 40 Diesel Storage Tank "A"/850
-35 3/0 RAB 41 Diesel Storage Tank "B"/852
-35 3/0 WATERFORD - UWii 3 3/4 3-52 Amendment No. 3 e
TABLE 3.3-11 (Cantinued)
FIRE DETECTION INSTRUMENTS TOTAL NUMBER OF INSTRUMENTS
- ELEVATION HEAT FLAME SM0KE ZONE ROOM NAME/ NUMBER (ft)
{x/y} (x/y) (x/y) 2.
REACTOR CONTAINMENT BUILOING**
RCB 1 Annulus /420***
+46 2/0 l
RCB 2 Electrical Penetration Area A
+21 24/0 RCB 3 Electrical Penetration Area B
+21 21/0 RCB 4 Reactor Cable Trays
+46 16/0 CT 1&3 Wet & Dry Cooling Tower "A" Cable Tray 1/0 CT 2&4 Wet & Dry Cooling Tower "B" Cable Tray 1/0 3.
FUEL HANDLING BUILDING FHB 2 Purification Pump Room /B155, Fuel Pool
+1 10/0 Pump "A"/B157, Fuel Pool Pump "B"/
B156, Fuel Pool Heater Exchanger /
B158 and Access Area /B-161 Emergency Filter Train Unit /8152
+1 6/0 Emergency Elect. Equip. Room /B151
+1 1/0 4.
CHARCOAL AIR FILTER UNITS E-35 (3A-SA) FHB Emergency Filter Train "A"
+1 1/0 E-35 (38-SB) FHB Emergency Filter Train "B"
+1 1/0 E-17 (3A-SA) Shield Building Ventilation
+46 1/0 System Filter Train "A" E-17 (3B-SB) Shield Building Ventilation
+46 1/0 System Filter Train "B" E-23 (3A-SA) Controlled Ventilation Area
+46 1/0 System Filter Train "A" E-23 (3A-SB) Controlled Ventilation Area
+46 1/0 System Filter Train "B" S-8 (3A-SA) Control Room Emergency Filter
+46 1/0 Train "A" S-8 (38-58) Control Room Emergency Filter
+46 1/0 Train "B" TABLE NOTATIONS
- (x/y):
x is the number of Function A (early warning fire detection and notification only) instruments.
l y is the number of Function B (actuation of fire suppression systems and early warning and notification) instruments.
- The fire detection instruments located within the containment are not required to be OPERABLE during the performance of Type A containment leakage rate tests.
This segment of duct is physically located 1
in the RAB H&V Equipment Room (299).
WATERFORD - UNIT 3 3/4 3-53 AMENDMENT NO. I5. 24, 31
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- Nj.';.vis' A !Cs t00$( ;A;f O(1(Cli_0h 1N$TRUMENTAfiCh j
TIM 111s CON?lil0s FOR OP(RAtl0N l
3.3.3.9 ine loose part detection syste.. Sna11 ee OPERABtt.
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APPLICABILITY:
MODES 1 and 2.
ACTION:
With one or more loose part detection system channels inoperable for a.
more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days j
outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
The provisions of Specifications 3.0.3 and 3.0.4 are not appilcable.
b.
SURVEllLANCE REQUIREMENTS
- 4. 3. 3.9 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of:
4.
a CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a
b.
a CHANNEL FUNCTIONAL TEST at least onct per 31 day!., and l
c.
a CHANNEL CAL 1 BRAT 10N at least once per 18 months.
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR RFACTOR REGULATION SUPPORTING AMENDMENT N0. 31 TO FACILITY OPERATING LICENSE NO NPF-38 LOUISIANA POWER AND LIGHT COMPANY WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By application dated December 11, 1987, as supplemented by letter dated December 22, 1987 Louisiana Power and Light Coipany (LP&L or the licensee) requested changes to Facility Operating License No. NPE-38 for Waterford Steam Electric Station, Unit 3 (Vaterford 3). The proposed changes would revise Technical Sp?cification Liniting Condition for Operation (LCO) 3.3.3.8 and its associated Table 3.3-11 to implement a proposed change in method of fire detection for the annulus wherein the current systen will be replaced with fire detection instrumerts mounted on the Annulus Negative Pressure System (ANPS) ductwork.
2.0 DISCUSSION The licensee has proposed to change the method of fire detection for the annulus area, citing the desire for a more accessible and improved detection system af. the primary reason for replacing the existing system.
The licensee has met with the staff to discuss this change, and has documentation describing the proposed systen and demonstrated that the changes will not reduce the level of fire protection at Waterford 3.
The existing annulus fire detection system conFists of 69 ionization type moke detectors circling the annulus in three loops at elevations -4,
+?l, and +46.
These three loops comprise two zores of detection for alarm purposes. The proposed fire detection system consists of two pho+.oelectric smoke detectors rounted on the ANPS duckwork with sample tubes penetratirg into the duct. The ANPS cperates continuously during normal plant operation to maintain the annulus negative pressure greater than five inches water gauge in accordance with TS 3.6.6.2.
Table 3.3-11 lists fire detection instrunerts, by function and location, which are subject to the LCO and Survaillance Requirements of Technical Specification 3/4.3.3.8. The proposed changes to Table 3.3-11 consists of reducino the number of Function A detection instruments from 69 to two, the number of zones from two to one; and indicating detectier at olevation '46 only.
Futber, a factnote util be added to the table tn a
clarify that the fire detection instruments for the annulus are physically l
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7 installed on the ANPS doctwork in the RAB. The charge to Statercrt c of TS 3.3.3.8 does not change the intent of the statement, but rather modifies the language to be consistent with the proposed system configuration. As a result of moving the detection inntruments to a location cutside the annulus, the surveillance interval requirements of TS 4.3.3.8.1 and 4.3.3.8.2 will change from "each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless perfomed ir the previous 6 months" to "at least once per C renths".
However, this occurs within the context of the existing surveillarce requirement language.
3.0 EVALUATION The proposed Technical Specification changes will implement a proposed charge in the arrulus fire detectinn systen. The staff reviewed information providrd by the licensee relative to the fire detection system change as part of its evaluation of the proposed Technical Specification change.
The inferration which has been provided indicates that conditions in the annulus provide little opportunity for a fira to occur. These unfaverable conditions include: minimal combustible loading; an absence of ignition sources; low oxygen concentration; and strict control of transient combus-tibles and access to the annulus. The licensee has verified operability of the proposed system by perfoming a field test of a neck-up which j
closely approxinates the proposed system design. An added measure of assuraece that the proposed modification will provida appropriate protec-tien for the atterdent hazards is found in the fact that penetratiens traversire the annulus are located below and in the same relative vicinity of the annulus as the intake duct of the ANPS. Thus, combustion byproducts originating at or near the penetratiers are expected to be rapidly pulled into the AFPS intake duct and quickly sensed by the smoke detectors mounted therein.
In addition, the preposed changes will ircrease system reliablity through the elimination er significant reduction in spurious alann, and the accessiblity of detectien instrumerts for reintenance activities and surveillance testing, thus reducing rarsonnel exposure.
The staff concludes that the proposed changes to Technical Specification LCO 3.3.3.8 and its asscciated Table 3.3-11, result in an acceptable level of fire protection, are consistent with the provisions of Branch Technical Position CHEB 9.5-1, and are, therefore, acceptable.
4.0 CM' TACT WITH STATE OFFICIAL The NRC staff has edvised tha Administrater, Nuclear Energy Division, 1
Office of Environmental Affairs, State of Louisiana of the proposed i
datermination of no significant hazards consideration. No corrents were received.
5.0 ENVIRONMENTAL CONSIDEPATION The amendrent relates to changes in installation or use of a facility component located within the restricted area as dafired in 10 CFP Part 20.
The staff has detemined that the amendment involves nn significant increase in the amounts and no sigrificant charge in the types of any effluents thet may be released offsite and that there is no significant
s
, increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendrent involves no significant hazards consideration ard there has been no public comment on such finding. Accordingly, the amandment meets the eli criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)gibility Pursuant to 10 CFR 51.22(b). no ar.vironmental impact statenent or environ-mental assessrent need be prepared ir connection with the it.cuance of this amendment.
6.0 CONCLUSION
Based upon its evaluatice of the proposed changes to the Waterford 3 Technical Specificatiens, the staff has concluded that: there is reason-able assurance that the haalth and safety of the public will not be endangered by creration in the proposed marrer, and such activities will be cerducted in compliance v:ith the Commission's reculatiors and the issuance of the arendment will not be inimical to the comron defense and security nr to the health ar.d safety of the public. The staff, therefore, concludes that the proposed changes are acceptable, and are hereby incorperated inte the Waterford 3 Technical Specificetions.
Dated: March 4.1988 i
Principel Contributor:
J. Wilson i
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