ML20212Q326

Forwards 860826 Final Hazards Summary Rept Update & Cross Index,Per Ipsar (NUREG-0828).Exemption from Schedular Requirements of 10CFR50.71(e) Re Update to Fsar,Requested. Fee Paid

ML20212Q326
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/27/1986
From:	Berry K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
References
RTR-NUREG-0828, RTR-NUREG-828 NUDOCS 8609040207
Download: ML20212Q326 (22)

Text

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oeneret offices: 1945 West Parnell Road, Jackson, MI 49201 . (517) 788-0550 August 27, 1986 Director, Nuclear Reactor Regulation -

US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - SUBMITTAL OF FINAL HAZARDS

SUMMARY

REPORT UPDATE AND REQUEST FOR EXEMPTION FROM THE SCHEDULAR REQUIREMENTS OF 10CFR 50.71(e)(3)(ii) .

This letter submits the Big Rock Point Final Hazards Summary Rt. port (FHSR)

Cross Index as described in the " Final Integrated Plant Safety Assessment Report" (IPSAR), NUREG-0828, and the Big Rock Point Intregrated Plant Issue "

A-35B. This letter also includes a request for a schedular exemption from the requirements of 10CFR 50.71(e)(3)(ii) to allow time to resolve NRC concerns.

10 CFR 50.71(e) requires each licensee of a nuclear power reactor to periodi-cally update the FSAR originally submitted as part of the application for an operating license. The initial update of the FSAR for plants licensed prior to July 22, 1980 was required to be submitted to the HRC no later than to July 22, 1982. However, for those plants initially subject to the NRC systematic evaluation program (SEP), 10 CFR 50.71(e)(3)(ii) provided that the updated FSAR was to be submitted within 24 months after notification of completion of the program. The Big Rock Point Plant as one of the plants chosen to be evaluated as part of the SEP was therefore subject to the provisions of 10 CFR 50.71(e) (3)(ii) . By a letter dated August 27, 1984, the NRC provided the

" Final Integrated Plant Safety Assessment Report" (IPSAR), NUREG-0828, docu-menting the completion of the SEP review for the Big Rock Point Plant and notifying Consumers Power Company that pursuant to 10 CFR 50.71(e)(3)(ii) we were required to submit a Final Hazards Summary Report as outlined in section 5.3.25.1 of the IPSAR within 24 months after the date of receipt, ie. Septem-ber 4, 1986. -

In a letter dated March 18, -1983, Consu:aers Power Company requested that the NRC expand its integrated assessment of topics identified in the SEP to include those issues currently affecting the Big Rock Point Plant but which were beyond the scope of the SEP. The up(ating of the Big Rock Point Final 8609040207 860827 .

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Director, NRR 2 Big Rock Point Plant Request for Schedular Exemption August 27, 1986 Hazards Summary Report (FHSR) was one of the issues that was included in thie l request. Section 5 of the IPSAR, provided the NRC conclusions associated with its review of these non-SEP topic items. Section 3.3.25.1 of the IPSAR identified Consumars Power Company's intention to evaluate a method of index-ing pertinent documents to provide a workable substitute to an updated FHSR and the staff conclusion that this proposal was acceptable. Since this is an

" Integrated Plan" Group A (Issue'A-35B) iten, a schedular exemption is being requested to 10CRF50.71(e)(3)(ii).

By a letter dated October 31, 1984, Consumers Power Company submitted a description of the program by which it proposed to provide the workable substitute to updating the Big Rock Point Plant FHSR. That method involved creating a permanent computerized database of pertinent docketed correspon-dence and a keyword / key phrase list that would be used to search the database.

A hard copy report showing the keywords / key phrases, the date of the letter, the topic and the location within CPCo of the letter that contained the keyword / key phrase would then be generated. The database, keyword / key phrase list, and the hard copy report would be updated on an annual basis. The NRC responded in a letter dated December 4, 1984 and stated that; "While the details of for implementing this system are not yet clear, the staff believes that the system being developed would be an acceptable alternative to an updated Final Hazards Summary Report." Consumers Power Company's conclusion that the method described was acceptable to the NRC was confirmed during a subsequent conference call between members of the NRC staff and Consumers Power Company personnel. The conference call was conducted on January 30, 1985, to discuss the details of the system and to address suggestions and staff recommendations contained in the December 4, 1984 NRC letter. Consumers Power Company had also submitted a copy of the report showing the results of a limited search of the database prior to this ccnference call. Thus, based on the results of that conferer.ce call, the preceding letters, and the finding contained in section 5.3.25.1 of the IPSAR, Consumers Power Company proceeded with the development and implementation of the the cross indexing program that had been described to the NRC.

This letter submits the hardcopy output of the computerized BRP FHSR Update cross indexing program. This document is being submitted to the NRC in lieu of an updated FHSR required by 10 CFR 50.71(e) and as approved by the NRC in Section 3.3.25.1 of the May 1984 Final IPSAR. The output is the result of the keyword search of docketed letters from January 1963 through February 1986 for letters sent to or received from Washington and from February 1961 through February 1986 for letters sent to or received frce NRC Region III. The listing, which will be updated annually, identifies detailed design information and provides a chronology of design tor the Big Rock Point Plant.

In addition to generating a hardcopy report, the data is accessible on an on-line basis using existing computer terminals. Both methods can and are being used by the Big Rock Point Plant staff to perform safety evaluations.

OC0886-0034S-NLO1

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Director, NRR 3 Big Rock Point Plant Request for Schedular Exemption August 27, 1986 Based on the use of the hardcopy report and the on-line system by Big Rock 4 Point personnel, Consurers Power Company has concluded that this system meets the intent of 10l CFR 50.71(e) in that it provides; a chronology of design changes to the Plant, identifies those safety evaluations performed by Consumers Power Company in support of license amendment requests, Safety Analyses developed by the NRC, and identifies other relevant material appearing on the Big Rock Point docket. Taken together, this material can be used by the Plant staff to identify the effects of design changes made to the

Plant over the life of the Plant.

The format of the output is as follows: at the top of each page is the key word or phrase. Note that for multiword phrases, such as "AC Power", the listing shows "AC ADJ POWER". The word "ADJ" is the contraction of " adjacent to" and instructs the computer to choose those letters which contain the complete phrase. Each detail line consists of Consumers Power Company's Correspondence Logging and Commitment Tracking System (CLCTS) Log Number, the group to which the letter was sent (either BRP, Region III, or Washington),

the Subject of the letter as it appears in (CLCTS), and the Cart / Frame number of the microfilm copy of the letter. The CLCTS Log Number consists of the '

I Plant ID (B),,an NRC ID (either Region or Washington), the date of the letter, i and a serial identifier (A, B, C, etc.) Not all the keywords that appear on I

the keyword list also appear in the printed output-since only those words that 4

result in a hit list of docketed letters are printed.

1 Request for Exemption from the Schedular Requirements of 10CFR 50.71(e)(3)(ii)

As noted above, Consumers Power Company identified an alternative to the requirements of 10 CFR 50.71(e) that was acceptable to both Consumers Power Company and the NRC. Based on our understanding that a system to index pertinent docketed correspondence was an acceptable alternative to an updated FHSR, Consumers Power Company initiated and completed a good faith effort to develop and implement the system. However, the NRC has recently identified concerns with the proposed system. Therefore, in order to provide sufficient time for the resolution of the NRC concerns, Consumers Power Company requests an exemption to the schedular requirements of 10 CFR 50.71(e)(3)(ii). The basis of this exemption request is explained above and satisfies the provi-sions of 10 CFR 50.12(2)(v). That is, the requested exemption would provide

- only temporary relief from the applicable regulation and Consumers Power Company has made a good faith effort to comply with the alternative to the regulation as agreed upon with the NRC and documented.in the IPSAR. An assessment of the environmental impact of the proposed exemption is presented below.

OC0886-0034S-NL01

Director, NRR 4 Big Rock Point Plant j Request for Schedular Exemption 1 August 27, 1986 ENVIRONMENTAL ASSESSMENT Identification of Proposed Action The proposed action would be for the NRC to grant an exemption from the requirements of 10 CFR 50.71(e)(3)(ii) to submit an updated FHSR for the Big l Rock Point Plant with in 24 months of the receipt of a letter notifying the i licensee that the systematic evaluation program has been completed. As noted i above, Consumers Power Company was notified by a letter dated August 27, 1984 that the SEP program had been completed for the Big Rock Point Plant. Consum-ers Power Company la requesting by this letter an exemption from the schedular requirements of 10 CFR 50.71(e)(3)(ii) in order to allow time for the NRC t

staff and Consumers Power Company to resolve the staff concerns with the enclosed alternative to providing an updated FHSR.

The Need for the Proposed Action Consumers Power Company, by a letter dated March 13, 1983, requested that the updating of the Big Rock Point FHSR be included in an expanded assessment of outstanding regulatory requirements. The primary purpose of this request was.

to better manage Plant resources applied to regulatory and non-regulatory tasks.

Consumers Power Company proposed that a method of indexing pertinent documents which would provide a chronology an identification of design changes to the Big Rock Point Plant would serve as a workable substitute to an updated FHSR.

In NUREG-Q828, transmitted to'CPCO by NRC letter dated August 27, 1984, the '4 NRC concluded that this proposal was acceptable. Subsequently the NRC identi-fled a concern that the proposed substitute may not constitute a completely adequate alternative to an updated FHSR. Therefore, a schedular exemption is required in order to allow time for Consumers Power Company and the NRC to resolve the NRC's concerns.

Environmental Impact of the Proposed Action This request for exemption involves only the required date for submittal of a document describing the as built condition of the Big Rock Point Plant and does not increase the risk of facility accidents. Thus, the proposed exemp-tion does not involve any increase in the likelihood of the release of radio-active or non-radioactive effluents from those already determined, nor does the proposed action have any other environmental impact. Therefore, Consumers Power Company has determined that the environmental impact of granting the exemption is insignificant.

Alternatives to the Proposed Action Consumers Power Company has concluded that there is no measurable impact

associated with the proposed exemption, therefore alternatives with equal or greater environmental impact to the proposed action have not been evaluated.

OC0886-00345-NL01

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Director, NRR -

5 Big Rock Point Plant Request for Schedular Exemption August 27, 1986 The principal alturnative would be to deny the exemption request however, such action would not provide any increase in the protection of the environment and would result in a significant diversion of Consumers Power Company resources from other work of greater significance to safety.

Finding of No Significant Impact Consumers Power Company has determined, based on our assessment of the envi-ronmental impact of the requested action, that there will not be a significant impact on the quality of the human environment.

A check in the amount of $150.00 (approval fee) is being submitted in accordance with 10 CFR 170.12(c).

I h Kennet W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point

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s Big Rock Point Plant- r Docket 50-155 I

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1 i i FINAL HAZARDS

SUMMARY

REPORT UPDATE -

August 26, 1986  ;

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BRP FHSR UPDATE KEY WORD LIST KEY WORD / PHRASE 1 AC POWER 2 AC POER SUPPLY 3 ACCESS CONTROL 4 ACCIDENT ANALYSIS 5 ACCIDENT

SUMMARY

6 ACCUMULATOR 7 ACID 8 ADMINISTRATION 9 ADSORBER 10 AIR EJECTOR 11 AIR LOCK 12 AIR OPERATED VALVE 13 AIR QUALITY 14 AIR SAMPLER 15 AIRBORNE RELEASE 16 ALARA 17 ALERT 18 ALTERNATE SHUTDOWN BUILDING 19 ALTERNATE SHUTDOWN PANEL 20 ALTERNATE SHUTDOWN SYSTEM 21 -AMPLIFIER 22 ANALYZER 23 ANCHOR 24 ANCHOR BOLT 25 ANION 26 ANNUNCIATOR 27 ANTICIPATED TRANSIENT WITHOUT SCRAM 28 APPENDIX R 29 AREA MONITORING 30 AREA MONITORING SYSTEM 31 AREA RADIATION MONITOR 32 AREA RADIATION MONITORING 33 ARGON 34 ASSOCIATED CIRCUITS 35 ATMOSPHERIC 36 ATOMIC SAFETY AND LICENSING BOARD 37 ATOMIZING 38 AUTOMATIC RECIRCULATION PUMP TRIP 39 AUXILIARY BUILDING 40 AUXILIARY COOLING SYSTEM 41 AUXILIARY FEEDWATER 42 AUXILIARY OPERATOR 43 AUXILIARY ROD INJECTION 44' AVERAGE PLANAR LINEAR HEAT RATE 45 BACKWASH UPDATE LIST

46 BALER

'47 BALL VALVE 48 BANK 49 BASKET STRAINER 50 BATTERIES 51 . BATTERY 52 BEARING 53 BIOLOGICAL SHIELD 54 BLEED

. 55 BLOCK VALVE 56 BLOWDOWN 57 BOILER 58 BOOSTER PUMP 59 BORATED 60 B0 RATION 61 BORIC ACID 62 BORON 63 BRAZED .

64 BREATHING AIR 65 BUILDINGS AND STRUCTURES 66 BURNABLE 67 BUS 68 BUS COOLING 69 BUTTERFLY

.70 CABINET 71 CAMERA 72 CANAL 73 CARBON FILTER f 74 CARD READER

.75 . CASK DROP 76 CAST IRON l

77 CATHODIC l 78 CATHODIC PROTECTION

( -79 CATION l

80 CAUSTIC l 81 CAVITATION 82 CAVITY 83 CENTRIFUCAL 84 CHARCOAL 85 CHARGER 86 CHECK VALVE 87 CHEMICAL ADDITION 88 CHEMICAL CONTROL l 89 CHEMICAL WASTE

-90 CHIMNEY 91 CHLORINATION 92 CHLORINE 93 CIRCUIT BREAKER 94 CIRCULATING 95 CIRCULATING WATER I

-96 CIRCULATING WATER SYSTEM P I

UPDATE LIST L _ - . _ .

I 97 CIRCULATION 98 CIVIL 99 CLAD 100 CLADDING 101 CLEAN RADWASTE 102 CLEAN-UP DEMINERALIZER 103 CLOSED LOOP 104 CLUTCH 105 COAXIAL 106 COBALT 107 COLUMN 108 COMBUSTIBLE CAS 109 COMMON CAUSE 110 COMMUNICATION 111 COMMUNICATION SYSTEM 112 COMPACTOR 113 COMPONENT COOLING SYSTEM 114 COMPONENT COOLING WATER 115 COMPOSITE SAMPLER 116 COMPRESSOR 117 COMPUTER 118 CONCRETE 119 CONDENSATE DEMINERALIZER 120 CONDENSATE SYSTEM 121 CONDENSATE TRANSFER 122 CONDENSATE TRANSFER SYSTEM 123 CONDENSER COOLING 124 CONDUCTOR 125 CONDUIT 126 CONNECTOR 127 CONSTANT 128 CONTAINMENT AIR LOCK 129 CONTAINMENT ATMOSPHERE HUMIDITY MONITOR 130 CONIAINMENT GAMMA MONITORS 131 COSTAINMENT INTEGRATED LEAK RATE TEST l 132 CONTAINMENT ISOLATION SYSTEM j 133 CONTAINMENT ISOLATION VALVES 134 CONTAINMENT PURGING 135 CONTAINMENT SPRAY 136 CONTAINMENT SPRAY VALVES 137 CONTAINMENT SUMP 138 CONTAINMENT VACUUM RELIEF 139 CONTAINMENT VENTILATION VALVES 140 CONTROL OF HEAVY LOADS 141 CONTROL OPERATOR i 142 CONTROL ROD l 143 CONTROL ROD DRIVE I 144 CONTROL ROD DRIVE MECHANISM 145 CONTROL ROD DRIVE SYSTEM 146 CONTROL ROD WORTH 147 CONTROL ROOM UPDATE LIST

148 CONTROL ROOM DESIGN REVIEW 149 CONTROL ROOM HABITABILITY 150 CONTROL SYSTEM 151 COOLANT FUMP 152 C00LDOWN 153 COOLER 154 C0 CLING WATER 155 CORE DIFFERENTIAL PRESSURE 156 CORE SPRAY COOLING '

157 CORE SPRAY COOLING SYSTEM 158 CORE SUPPORT 159 COUNTER 160 COUNTING AND MEASURING EQUIPMENT 161 COUPLING 162 CRACKING 163 CRANES 164 CRITICAL FUNCTIONS 165 CRITICAL FUNCTIONS MONITORING 166 CRUD 167 CUBICLES 168 CYLINDERS 169 DAMPER 170 DC POWER 171 DC POWER SUPPLY 172 DEBRIS SCREEN 173 DECAY HEAT 174 DECAY HEAT REMOVAL 175 DECONTAMINATION 176 DEGRADED VOLTAGE TRIP SYSTEM 177 DELUGE 178 DEMINERALIZED 179 DEMINERALIZED WATER 180 DEMINERAL12ED WATER SYSTEM 181 DEMISTER 182 DENSITY

! 183 DEPRESSURIZATION VALVE 184 DEPTH 185 DESIGN BASIS ACCIDENT 186 DEVIATION REPORT 187 DEWATERING 188 DEWPOINT 189 DIAPHRAGM 190 DIESEL GENERATOR 191 DIFFERENTIAL PRESSURE 192 DIFFUSERS 193 DIFFUSION 194 DIGITAL i 195 DILUTION 196 DIODE 197 DIRTY RADWASTE 198 DISC UPDATE LIST

199 DOMESTIC WATER 200 DOM.".STIC WATER SYSTEM 201 DOOR 202 DOSE 203 DOSIMETER 204 DOWNCOMER 205 DRUM LEVEL 206 DRYER 207 DUCT 208 DUCTWORK 209 EFFLUENT

.210 EJECTOR 211 ELECTRICAL EQUIPMENT QUALIFICATION 212 ELECTRICAL PENETRATION 213 ELECTRO-HYDRAULIC CONTROL SYSTEM 214 ELECTRONIC 215 ELECTR0 PNEUMATIC 216 ELEMENT 217 ELEVATOR 218 EMBRITTLEMENT 21@ EMERGENCY AIR LOCK 220 EMERGENCY CONDENS3R 221 EMERGENCY CONDENSER SYSTEM 222 EMERGENCY COOLING SYSTEM 223 EMERGENCY CORE COOLING 224 EMERGENCY CORE COOLING SYSTEM 225 EMERGENCY DIESEL 226- EMERGENCY DIESEL GENERATOR 227 EMERGENCY ESCAPE HATCH 228 EMERGENCY NOTIFICATION NETWORK 229 EMERGENCY OPERATING PROCEDURES 230 EMERGENCY OPERATIONS FACILITY 231 EMERGENCY PLANNING 232 EMERGENCY POWER 233 EMERGENCY POWER SYSTEM 234 EMERGENCY PROCEDURES 235 EMISSION 236 ENCLOSURE SPRAY SYSTEM 237 ENGINEERED SAFETY FEATURES 238 EQUIPMENT HATCH 239 EROSION 240 ESTIMATED CRITICAL POSITION 241 EVAPORATOR 242 EVENT REPORT 243 EXCURSION 244 EXPLOSIVE 245 EXPLOSIVE VALVE 246 EXTENSION TANK 247 EXTERNAL FUEL CYCLE 248 EXTRACTION 249 EXTRACTION HEATER DRAINS UPDATE LIST

250 EXTRACTION STEAM 251' FACILITY CHANGE 252 FAILED FUEL 253 FAULT ,

254 FEEDWATER CONTROL 255 FEEDWATER FLOW 256 FEEDWATER PURITY SYSTEM 257 FEEDWATER RECIRCULATION 258 FEEDWATER RECIRCULATION SYSTEM 259 FEEDWATER SYSTEM 260 FENCE 261 FENCING 262 FINAL HAZARDS

SUMMARY

REPORT 263 FIRE BARRIER 264 FIRE HAZARDS ANALYSIS 265 FIRE PROTECTION 266 FIRE PROTECTION SYSTEM 267 FISH 268 FITTINGS 269 FLAMMABLE 270 FLEXIBLE 271 FLOOD 272 FLOW CHA' THEL 273 FLOW CONTROL 274 FLOW CONTROL SYSTEH 275 FLOW ELDIENT 276 FLUSH 277 FLUX 278 FOUNDATION 279 FREEZE 280 FUEL BUNDLE 281 FUEL CHANNEL 282 FUEL CLADDING FAILURE 283 FUEL FAILURE 284 FUEL HANDLING 285 FUEL HANDLING ACCIDENT 286 FUEL HANDLING SYSTEM 287 FUEL INSPECTION 288 FUEL OIL 289 FUEL POOL 290 FUEL SYSTEM 291 GAGE BLOCKS 292 CAP 293 GAS IGNITOR 294 CAS PROCESS RADIATION MONITORING 295 GASKETS 296 CATE

. 297 GATE VALVES 298 GAUGE 299 GENERAL EMERGENCY 300 GENERAL OFFICE CONTROL CENTER l.

UPDATE LIST

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301 GEOLOGY '

302: GLOBE 303 -GLOBE VALVES 304~ GRAB SAMPLES 305 GROUNDING 306 GUIDE TUBE

, ~307 HABITABILITY 308 HANGER 309 -HEALTH PHYSICS NETWORK 310 HEARINGS

,. 311 HEAT REMOVAL

312 HEAT SINK 313 HEAT TRACING 314 HEATER DRAIN 315 HEATING AND VENTILATION 316 HEATING VENTILATION AND AIR CONDITIONING' 317 HELB 318 HEPA TILTERS 319 HIGH ENERGY LINE BREAK

-320 HIGH PRESSURE 321 HIGH RADIATION TRIP 322 HOIST 323 HOLDUP 324 HUMAN FACTORS 325 HUMIDITY 326 HVAC 327 HYDRANT 328- HYDRAULIC 329 HYDROGEN 330 HYDROLOGY 331 HYPOCHLORITE 332 IGNITOR 333 IMPELLER 334 IN-CORE NEUTRON 335 IN-CORE NEUTRON MONITORING SYSTEM l' 1336 INITIAL PRESSURE REGULATOR 337 INSERVICE INSPECTION 338 INSTRUMENT AIR 339 INSULATION 340 INTAKE 341 INTAKE STRUCTURE 342 INTEGRATED LEAK RATE 343 .INTERGRANNULAR STRESS CORROSION CRACKING 344 INTERLOCK 345 INTERMEDIATE RANGE 346 INTRUSION 347 INVERTER

.348 ION EXCHANGE-349 ISOLATION VALVES 350 JET PUMP 351 JOINT PUBLIC INFORMATION CENTER UPDATE LIST

352 JUNCTION BOX 353 KEY SYSTEM 354 LAGGING 355 LAKE MICHIGAN 356 LAUNDRY WASTE 357 LEAD ANTIM0h'l 358 LEAK DETECTION 359 LEAK RATE TESTING 360 LEAK TESTING 361 LETDOWN 362 LETDOWN AND MAKEUP 363 ISTDOWN COOLING 364 LEVEL CONTROL 365 LEVEL CONTROLLERS 366 LEVEL SWITCH 367 LICENSEE EVENT REPORT 368 LIFTING DEVICES 369 LIMITING CONDITION OF OPERATION 370 LIQUID POISON SYSTEM 371 LIQUID PROCESS MONITORING 372 LIQUID PROCESS MONITORING SYSTEM 373 LOAD SEQUENCE 374 LOAD SHEDDING 375 LOCAL POWER RANGE MONITOR 376 LOCKS 377 LOG N 378 LOG POWER 379 LOOSE PARTS 380 LOOSE PARTS MONITORING SYSTEM 381 LOSS OF COOLANT ACCIDENT 382 LOSS OF OFF-SITE POWER 383 LOSS OF OFFSITE POWER 384 LOSS OF ON-SITE POWER 385 LOUVER 386 LOW PRESSURE INJECTION SYSTEM 387 LOW-PRESSURE

! 388 LUBRICANT i

389 LUBRICATION 390 MAGNETIC 391 MAIN CONDENSER l 392 MAIN POWER TRANSFORMER l 393 MAIN STEAM BYPASS VALVE 394 MAIN STEAM ISOLATION 395 MAIN STEAM ISOLATION VALVE 396 MAIN STEAM SYSTEM l 397 MAKE-UP i 398 MAKEUP SYSTEM 399 MAKEUP WATER 400 MANIFOLD 401 MANUAL CONTROL 402 MASONRY UPDATE LIST

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403 MAXIMUM CREDIBLE ACCIDENT

-404 MEASURING AND TEST EQUIPMENT 405 MECHANICAL VACUUM PUMP 406 MEGAWATTS ELECTRIC 407 MEGAWATTS ELECTRICAL 408 MEGAWATTS THERMAL 409 METEOROLOGY 410 METER 411 MICROMETER 412 MISSILES 413 MIXED BED 414 MOISTURE 415 MOTION DETECTION 416 MOTOR CONTROL CENTER 417 MOTOR GENERATOR SET 418 MOTOR OPERATED VALVE 419 MOTOR OPERATOR 420 NATURAL CIRCULATION 421 NEUTRON DETECTOR 422 NEUTRON MONITORING 423 NEUTRON MONITORING SYSTEM 424 NEUTRON SOURCE 425 NEUTRON WINDOW 426 NEW FUEL 427 NICKEL CADMIUM 428 NITROGEN SUPPLY 429 NOISE 430 NUCLEAR DATA LINK SYSTEM 431 NUCLEAR PERSONNEL ADMITTANCE SYSTEM 432 NUCLEAR STEAM SUPPLY 433 NUCLEAR STEAM SUPPLY SYSTEM 434 NUREG 435 0 RING 436 0-RING 437 0FF GAS 438 0FF GAS ISOLATION 439 0FF GAS TREAThENT SYSTEM 440 0FF-GAS SYSTEM 441 0FFSITE 442 OIL 443 OIL COOLER 444 OPERATIONAL SUPPORT CENTER 445 0UTAGE 446 0UTFALL 447 OVEN 448 OVER LOAD 449 OVEREXPOSURE 450 67ERFLOW 451 0'/ERHEATING 452 OVERPRESSURIZATION 453 OVERSPEED UPDATE LIST

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454 OXYGEN

'455 PENTRABORATE

i. .456 PERIM-ALERT 457 PERISCOPE 458 PERSONNEL ACCOUNTABILITY 459 PH- ,

460 PILOT VALVE 461 PIPE BREAK 462 PIPE RESTRAINTS 463 PIPF, TUNNEL BLOWOUT PANEL 464 PLANT PROTECTION 465 PLANT PROTECTION AND SECURITY SYSTEM 466 PLANT TRIP 467 PLUG 468 PLUG VALVE 469 PNEUMATIC

-470 POSITION INDICATION 471 POST INCIDENT COOLING SYSTEM

.472 POST INCIDENT SYSTEM 473 POST-INCIDENT COOLING 474 POST-INCIDENT SYSTEM

'475 POTABLE WATER 1 476 POWER SYSTEM 477 PRESSURE CONTROLLER 478 PRESSURE RELIEF 479. PRESSURE SENSORS 480 PRESSURE VESSEL 481 PRIMARY COOLANT SYSTEM 482 PRIMARY LOOP PIPING 483 PRIMARY SYSTEM ISOLATION FAILURE 484 PROBABILISTIC RISK ASSESSMENT 485 PROCESS INDICATOR

-486 PROCESS RADIATION MONITOR 487 PROCESS RADIATION MONITORING 488 PROCESS STEAM 489- PROTECTIVE RELAY 490- PROTECTIVE RELAYING 491 PUBLIC ADDRESS 492 PUMP HOUSE I

493 PURGE 494 PURIFICATION 495 QUALITY CONTROL 496 RADIATION AREA MONITORS

-497 RADIATION MONITORS 498 RADIOACTIVE GASEOUS EFFLUENT MONITOR 499 RADIOACTIVE WASTE 500 RADIOLOGICAL EFFECTS 501 RADIOLOGICAL EFFLUENTS 502 RADWASTE SYSTEM j 503 RAIL

! 504 RAILROAD UPDATE LIST

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505 REACTOR BUILDING 506 REACTOR CAVITY 507 REACTOR CLEANUP SYSTEM 508 REACTOR COOLANT SYSTEM VENTS 509 REACTOR COOLING WATER 510 REACTOR CORE .

511 REACTOR DEPRESSURIZATION SYSTEM 512 REACTOR FLANGE 513 REACTOR HEAD.

514 REACTOR INSTRUMENTATION 515 REACTOR INTERNALS 516 REACTOR NEUTRON MONITOR 517 REACTOR OPERATOR 518 REACTOR POWER MONITORS 519 REACTOR PRESSURE SIGNAL 520 REACTOR PROTECTION 521 REACTOR PROTECTION SYSTEM 522 REACTOR SAFETY STUDY

, 523 REACTOR SAFETY SYSTEM 524 REACTOR SHUTDOWN COOLING SYSTEM 525 REACTOR TRIP SYSTEM 526 REACTOR VESSEL INTERNALS 527 READER 528 RECEIVER 529 RECIRCULATING PUMP 530 RECIRCULATION PUMP TRIP 531 RECORDER l 532 RECTIFIER

. 533 REGULATOR 534 RELAY SYSTEM 535 RELAYING i 536 RELAYS 537 RELIEF 538 RELIEF VALVE 539 RESIDUAL HEAT REMOVAL 540 RESIN RECENERATOR 541 RESIN TRANSFER 542 RESINS 543 RHEOSTAT 544 ROD DRIVE CATCHER 545 ROD DROP ACCIDENT l 546 ROTOR 547 RUPTURE DISC

548- SAFFGUARDS 549 SAFETY ANALYSIS 550 SAFETY ANALYSIS REPORT 551 SAFETY AND RELIEF 552 SAFETY EVALUATION I 553 SAFETY EVALUATION REPORT l 554 SAFETY INJECTION 555 SAFETY PARAMETER DISPLAY

UPDATE LIST

556 SAFETY RELIEF 557 -SAFETY SYSTEMS 558 SAHPLER 559 SAMPLERS 560 SANITARY 561 SCRAM 562 SCRAM DISCHARGE TANK 563 SCRAM DUMP TANK 564 SCRAM VALVE 565 SCREEN 566 SCREEN HOUSE 567 SEAL AND LUBE OIL 568 SEAL COOLING 569 SEAL FAILURE 570 SEAL INJECTION 571 SEAL OIL 572 SEALS 573 SECONDARY 574 SECURITY 575 SEICHE 576 SEISMIC 577 SEISMIC INSTRUMENTATION 578 SEISMOLOGY 579 SENIOR REACTOR OPERATOR 580 SENSORS 581 SEQUENCER 582 SERVICE AIR 583 SERVICE WATER

'584 SET POINT 585 SEWAGE AND CHLORINATION 586 SHIELD COOLING 587 SHIELDING 588 SHUTDCWN COOLING 589 SHUTDOWN COOLING SYSTEM

-590 SIMULATOR 591 SIRENS 592 SITE AREA EMERGENCY 593 SMOKE -

594 SNUBBER 595 SODIUM PENTABORATE 596 SOLENOID VALVE 597 SOLENOIDS 598 SOLID 599 SOLID RADWASTE

600 SOUND POWERED 601 SOUND-POWERED 602 SOURCE RANGE 603 SPARGER 604 SPECIlfEN 605 SPEED 606 SPENT FUEL UPDATE LIST

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607 SPENT FUEL POOL 608 SPENT FUEL POOL MAKEUP 609. SPENT FUEL RACK 610 SPRINKLER 611 . SQUIB

-612 STACK GAS 613 STACK GAS MONITOR 614 STACK GAS MONITORING 615 STAINLESS 616 STAINLES3 STEEL 617 STANDARD OPERATING PROCEDURES 618 START-UP 619 STARTERS 620 STARTUP 621 STATION POWER 622 STATION POWER TRANSFORMER 623 STEAM DRUM 624 STEAM DRUM BLOWOUT PANEL 625 STEAM DRUM SAFETY RELIEF VALVES 626 STEAM DUMP TANK 627 STEAM LINE BREAK l 628 STEAM SEAL 629 STEAM SUPPLY 630 STEAM TRAP 631 STOP CHECK 4

632 STOP VALVE 633 STOP-CHECK 634 STORAGE RACK 635 STRAINER 636 STRESS 637 STRUCTURAL 638 STUDS 639 SUBSTATION 640 SUMP i 641 SUMP LEVEL l 642 SUMP PUMP 643 SUMP SYSTEM 644 SUPPORT 645 SURVEILLANCE TEST 646 SURVEILLANCE TESTING l 647 SWING CHECK j' 648 SWING-CHECK f

649 SWITCHYARD 650 SYSTEMATIC EVALUATION PROGRAM i

651 TECHNICAL SUPPORT CENTER 652 TELEPHONE 653 TELEVISION 654 THERMAL CUTOUT 655 THERMAL OVERLOAD 656 THERMAL PROTECTION 657 THERMAL SHIELD UPDATE LIST l., _ _ . - _

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l 4: l 658 THERMOCOUPLE 659 THERM 0 LUMINESCENCE DOSIMETERS 660 THREE MILE ISLAND 661 TIMERS 662 TIMING RELAY 663 TIMING RELAYS 664 TORNADO 665 TORQUE 666 T0XIC GAS 667 TRANSFORMER 668 TRANSIENT 669 TRANSIENT ANALYSIS 670 TRANSMISSION 671 TRANSMISSION TOWERS 672 TRAP 673 TRASHRACK 674 TRAVELING WATER SCREEN 675 TRAY 676 TRIAX 677 TROLLEY 678 TURBINE BUILDING ,

679 TURBINE BYPASS VALVE 680 TURBINE GENERATOR 681 U-TUBE 682 UNDERGROUND 683 UNINTERRUPTIBLE POWER SUPPLY 684 UNUSUAL EVENT 685 VACUUM 686 VALVE OPERATORS 687 VENTILATING 688 VENTILATION DAMPER 689 VESSEL LEVEL 690 VIBRATION 691 VISITOR 692 WARM WATER 693 WARMING 694 WATER BOX 695 WATER PROOF 696 WATER TIGHT 697 WEATHER 698 WELDS 699 WELL. WATER 700 WELL WATER SYSTEM l 701 WIND 702 WIRE 703 WYE STRAINER 704 X-RAY 705 XENCN l 706 YARD t

l UPDATE LIST

Proc No NOD-09 Page 11 of 11 Revision 1 Date REVIEWING, PROCESSING AND COMMENTING ON NEW OR REVISED REGULATORY DOCUMENTS Approved:

Director, Nuclear Licensing Date  ;

i i

NLD0186-085T-NLO3-TP12

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