BECO-97-096, Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-1433

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Application to Propose Changes to Tss,Relocating Radioactive Effluent TS & Radiological Environ Monitoring Program to Odcm,Per GL 89-01 & NUREG-1433
ML20211G211
Person / Time
Site: Pilgrim
Issue date: 09/19/1997
From: Boulette E
BOSTON EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211G216 List:
References
RTR-NUREG-1433 BECO-97-096, BECO-97-96, GL-89-01, GL-89-1, NUDOCS 9710020151
Download: ML20211G211 (12)
v • d • e


Text

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, 10CFR50.90 Boston Edhoon Pogrim Nuclear Power stat,on Rocky Hill Road Plymouth, Massachusetts 02360

, E. T. Boulette, PhD Senior Vice President - Nuclear Se tember 19, 1997 B Co 97-096 U. S. Nuclear Regulatory Commission Document Control Desk

. Washington, DC 20555 1

License DPR-35 Docket 50-293 Proposed Chanoes te the Pilorim Nuclear Power Station Radiolooical Effluent Technical Specifications

References:

1. NUREG 1433: " Standard Technical Specifications, General Electric Plants, BWR/4"
2. Generic Letter 89-01
" Implementation of Programmatic Controls for Radiological Effluent Technical Specifications and the Relocation of Procedural Details of RETS i and REMP to the Offsite Dose Calculation Manual"

- 3. LER 97-002-00, BECo letter dated 3/10/97 (2.97.030)

Boston Edison Company proposes changes to the Pilgrim Nuclear Power Station Technical t Specifications (TS) to relocate the Radioactive Effluent Technical Specifications (RETS) and the

, Radiological Environmental Monitoring Program to the Offsite Dose Calculation Manual (ODCM), in accordance with the recommendations of Generic Letter 89-01 and NUREG 1433. In order to minimize future revisions to plant programs and procedures, changes to other sections are also being proposed to

, align the current TS with NUREG 1433.

The proposed changes are summarized in Attachment A. This attachment also contains a matrix that

' identifies the documents and sections for all relocated information. Attachment B contains the revised Technical Specification pages. Attachment C contains:

. the marked-up existing technical specification pages /

. a discussion of change for each change e determination of No Significant Hazards Consideration 0

. revised PNPS Technical Specification pages

. the marked-up pages of NUREG 1433 where applicable

- 10 ,

. a discussion of deviations from NUREG 1433 where applicable.

The revised ODCM, with the relocated RETS for Pilgrim, is provided as Attachment D in accordance with GL 89-01.

The copy of this letter sent to Alan Wang, the Pilgrim Project Manager, includes a computer disk with the files in Word Perfect format.

f 7

1 9710020151 970919 Qggll!j[jy! ll j PDR ADOCK 05000293 . . . ' .

P PDR l

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' Boston Edison Co.

Paga 2 Should you have any questions regarding this submittal or our future submittal fnr the conversion to ,

standard technical specifications, please contact Charles Mathis at 508-830-8061 or Marie Lenhart at 1 508-830-7937.

l O (

8:.. T. Boulette, Ph.D.

MTUdmc/retsitr2 Commonwealth of Massachusetts )

County of Plymouth )

Then personally appeared before me, E. T. Boulette, who being duly sworn, did state that he is Senior Vice President - Nuclear of Boston Edison Company and that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best o i knowledge and belief.

My commission expires: M/lI-04.20dech

' DATE

_b/ /u >

10TARY PUBDy 1

i l Attachments: (A) Summary of Proposed Changes (B) Revised Technical Specification Pages (C) Technical Specification Change Packagd L (D) Draft Revised ODCM cc: Mr. Alan Wang, Project Manager Mr. Robert M. Hallisey, Director

Project Directorate I-3 Radiation Control Program

-Office of Nuclear Reactor Regulation Center for Communicable Diseases -

Mail Stop; OWF 1482 Mass. Dept. of Public Health l U. S. Nuclear Regulatory Commission 305 South Street 1 White Flint North 11555 Jamaica Plain, MA 02130 l

Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Mr. Jim Muckerheide Region i Mass. Emergency Management Agency 475 Allendale Road 400 Worcester Road King of Prussia, PA 19406 P.O. Box 1496 Framingham, MA 01701 Senior NRC Resident inspector Mr. Peter Laporte, Director Pilgrim Nuclear Power Station Mass. Emergency Management Agency

400 Worcester Road P.O. Box 1496 Framingham, MA 01701-0313

, Att: chm:nt A Page 1 of 10 Summary of Proposed Changes Summarv of Chanaes The proposed changes described below will revise the Pilgrim Nuclear Power Station (PNPS)

Radioactive Effluent Technical Specifications (RETS) and the Radiological Environmental Monitoring Program in accordance with Generic Letter 89-01. In order to minimize a future administrative burden associated with the conversion of PNPS Technical Specifications to standard technical specifications, revisions to sections 4.0, 5.0, and 6.0 are proposed to align the Technical Specifications with NUREG 1433.

The Table of Contents has been revised as necessary for the proposed changes.

DEFINITION (i., for the Offsite Dose Calculation Manual is incorporated into ITS 5.0, " Programs and Manuals", subsection 5.5.1, "Offsite Dose Calculation Manual (ODCM)".

DEFINITION (BB)

  • Member (s) of the Public"is relocated to the ODCM and its footnote is deleted.

DEFINITION (CC) " Site Boundary" is relocated to the ODCM.

DEFINITION (DD 1&2) for gaseous and liquid radwaste treatment systems are relocated to the ODCM.

TS 3/4.8 " RADIOACTIVE EFFLUENTS"is relocated to the ODCM with the following exceptions:

3.8.F.1. " Hydrogen Concentration in the Augmented Offgas System"is relocated to the FSAR.

4.8.F.2 " Hydrogen Concentration in the Augmented Offgas System"is relocated to the FSAR.

S/4.8.G " Main Condenser" is revised to be consistent with NUREG 1433, section 3.7.6 " Main Condenser Offgas", as supported by PNPS specific design and licensing bases, and 3/4.8.H " Mechanical Vacuum Pump"is revised to be consistent with NUREG 1433 and Supplemental Technical Specifications drafted by the BWROG Technical Specification Committee - A.

T3.8-2 The " Augmented Offgas Treatment System Monitor" is relocated to the FSAR.

! T4.8-4 The " Augmented Offgas Treatment System Monitor"is relocated to 15e FSAR.

TS 4.0

  • MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES"is relocated to the FSAR.

TS 5.0 " MAJOR DESIGN FEATURES"is renumbered 4.0, the title changed to " DESIGN FEATURES",

and revised in accordance with NUREG 1433, as supported by PNPS specific design and licensing basis.

I TS 6.0 " ADMINISTRATIVE CONTROLS" is renumbered 5.0 and revised in accordance with NUREG 1433 as supported by PNPS specific design and licensing basis. The following specific changes are proposed:

. Added the specification defining Nuclear Operations Supervisor responsibilities

. Editorial and format changes to Unit Staff requirements

. Major changes to the requirements for procedures l

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  • Att:chmtnt A I

Pcga 2 of 10 Summary of Proposed Changes

. Added a Programs and Manuals sections for.

?

Offsite Dose Calculation Manual Primary Sources Outside of Containment-Post Accident Sampling Radioactive Effluent Controls Program Component Cyclic or Transient Limit Technical Specification Bases Control Program

. ORC and NSRAC responsibilities are relocated to the FSAR

= Record retention is relocated to the FSAR

. Routine reports have been updated to current requirements

. High Radiation has been revised to be consistent with 10CFR20.

TS 7/8.0," RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM'is relocated to the ODCM in its entirety.

_ Schedule of Chanae This change will be effective within 30 days of receipt of approval from the NRC. Because this change is administrative in nature and follows the guidelines of Generic Letter 89-01, we request a review of this proposed change by December 31,1997

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Matrix of Changes / Relocations Current PNPS Tecsefilcal W '

w, sgm > < - ' 4. , - r avge <

_~ p ,

1.0 DEFINITIONS 1.0.Z Offsae Dose Calculaten Manual (COCM) ITS 5.5.1 Offsee Dose Calculaton Manual (ODCM) 1.0 BB Memberts)of the Pubhet ODCM 2.1 Member (s)of the Pubhc1 10CC See Boundary ODCM 24 See Boundary 10DD Radwaste Treatment System ODCM 2.3 Radweste Treatment System 1.0 DD_1 Gaseous Radwaste Treatment System ODCM 2.3 a Gaseous Radwaste Treatment System 10DD2 Lqud Radwaste Treatmera System CDCM 2.3 b LJguid Radweste Treatment System 3/4.8 RADIOACTNE EFFLUENTS 3/4 8 A Lsquid Emuents Concentraten ODCM 3/42.1 Lsquid Effluents C w L.Lvi.

38A1 concentration of radioactwe matenal released at any trne ODCM 321 concentraten of radcactwe rnatenal released at any time 3 8.A 1 Action Lurats exceeded, restore wi e.Lvi.withm ernets ODCM 3 2.1 Aden Lawts em weded, restore concentration withm hmits 4 8 A.1 determme radioactway content of each batch ODCM 42.1.a determene radcactway content of each batch 4 8 A.2 Use pre-release anatyses resuRs to assure withn kmsts ODCM 421.b use pre-release anaryses results to assure withm hmas 3/4 8 B Radmactwe Lsqud Emuent instrumentaten ODCM 3/41.1 Radcactwe Lsqued Effluent instrumentaten 3 8 B.1 instrumentaten channels shas be operable ODCM 3.1.1 Instrumentanon channels shan be operabie 3881a estrumentaten channet alarm /tnp setpoint less conservatwe ODCM 3 1.1.a metrumentation channet alarmanp setpoint less conservatwe 3 8 B.1 b one or rnore nstrumentaten channels inoperable ODCM 3.1.1.b one or more ristrumentaten channets moperable  !

4 8 B.1 determme setports for rnonnonng mstrumentaten ODCM 4 1.1.m determme setports for rnorwtonng ostrumentation 4882 estrur,entation channet shan be demonstrated operable ODCM 41.1 b notrumentaten channel shan be demonstrated operable 3/4 8 C Lsqud Radwaste Treatment ODCM 3,42.3 Legi.:vd Radweste Treatment 3 8 C.1 Lequid radweste treatment system maintamed & used ODCM 32.3 Uquid radwaste treatment system mantained & used 3 8 C.1 Action radioactNe hqued waste being discharged without treatment ODCM 323 Acton radcachve hquid waste bemg discharged without treatment 4 8 C.1 Calculate doses due to bqud releases ODCM 423a Cricuiste doses due to bqud releases 48C2 radwaste treatment system schemate ODCM 423b radwaste treatment system schemate 3/4 8 D Gaseous Emuents Dose Rate ODCM 3/43.1 Gaseous Effluents Dose Rate ,

38D1 restantaneous dose rate release Irnas ODCM 3.3.1 mstantaneous dose rate release innts 3 8 D 1.a restore the release rate to withm the hma(s). ODCM 33.1a restore the release rate to withm the kme(s).

48D1 Dose rate due to roble gases determined to be withm bmits ODCM 4.31.a Dose rate due to noble gases determoed to be withn hmas 48D2 Obtan representatue samples and perform anatyses ODCM 43.1b Obtan representatue samples and perform analyses 3/4 8 E Radioactwe Gaseous Emuent ODCM 3/4.12 Radmactwe Gaseous Effluent ,

3 8 E.1 Imstrumentation channets shaR be operable ODCM 3.12 hnstrumentaten channels shag be operable 3 8 E.1 a channel alarm!tnp setpoint less conservatwe ODCM 3.12a channet alarmanp setpoint less conservatse 3 8 E.1 b one or more estrumentabon channets snoperable ODCM 3.12b one or more instrur,entation channets anoperable 48E1 determme setpoints ODCM 412.a determne setponts >

4 8 E.2 Demonstrate rnonnonng nstrumentation channets operable ODCM 4.12b Demonstrate .evravii.g instrumenta'en channels operable I

Attachment A i 3 of 10 9/23/97821 AM

b Matfix of Changes / Relocations '

Castrent PNPS Technical SpectAcamone w s v wc cwa my y% ~

p:71 m. ; ; e vs,..

3/4 8 F Gaseous Effluert Treatment ODCM 3/4.3.4 Gaseous Effluent Treatmert 38F offgas system en service pnor to 50% reactor power ODCM 3.3.4 offges system in service pner to 50% reactor power 3 8 F a Acton gaseous effluents being discharged without treatment. ODCM 3.3 4 Achon gewous ef!luents being discharged wahout treatment.

3.8.F.1 concentratton lamet on hydrogers in augmented offges FSAR SA Gaseous Radweste System 3.8.F.1.a concentration > 1 emit on hydrogen in augmented offges FSAR SA Gaseous Radweste System 4 8 F.1 Venfled Augmented offges annunciator operabssty . ODCM 4.3.4.a Venfled Augmented offges annuncestor operatukty 4.3.F.2 Determine hydrogen concentration in augmented offgas FSAR 9.4 Gaseous Radweste System Figure 4 8-2 Gaseous Effluent Treatment schemanc ODOM 4.3.4 b Gaseous Effluert Treatmert system schemebc 3/4 8 G Man Condenser ITS 3/46.1 Maan Condenser 38G1 Gross radioactrvey noble gases release rate let ITS 3.81.1 Gross radcactrvity noble gases release rate Imt 3 8 G 1 Achon restore gross radioactrvey release rate to wrthen the let ITS 38.1A restore gross radioactrvey releese rate to withm the let iTS 3.8.1.B Requirements not met 4 8 G.1 a Determene release rate of noble gases (31 days) ITS 48.1.1 Determme release rate of noble gases (31 days) j 48G1b 50% average dady gross radioactivry release rate increase 50% average deny gross radioectrvey release rate increase 3/4 8 H Mecharwcal Vacuum Pump ITS 3/482 Mechenecal Vacuum Pump 3 8 H.1 Capabehty to isolate & secure on high radioactrvey segnal 1TS 3 82.A Inoperable Channels 38H2 hmas of Specification 3 8 H.1 are net met ITS 3.82B Requiremerts not met ITS 482.1 ChannetCheck [

ITS 4822 Cahbrate tnp unas ITS 4.82.3 Channet Cahbraten 48H1 venfy automatic secunng & sotation ITS 4824 venfy automatic secunng & esotaten (LSFT) >

TABLE 3 8-1 RADIOACTIVE UQUtD EFFLtJENT MONITORING ODCM Table 3.1-1 RADtOACTIVE UQUID EFFLUENT MONITORING INSTRUMENTATION T3 8-1.1 Gross Rad Monitors Providmg Automatic Termmation of ODCM T31-1.1 Gross Rad Mon. tors Providing Automatic Termmaten of l Release Release T3 8-1.1.a Liquid Radwaste Effluent Lme ODCM T3.1-1.1.a Liqued Radweste Effluent Line T3 8-12 Flow Rate Measuremert Devices ODCM T3.1-12 Flow Rate Measurement Dewsces j T3 8-1.2 a Lsquid Radwaste Emuert Line ODCM T3.1-12a Uqued Radweste Effluent Line T3 8-1.2 b Descharge Canap ODCM T3.1-12b Discharge Canaf T3 8-1 Note 1 Flow win bs eshmated based on ODCM T31-1 Note 2 Flow will be eshmated based on Note 2-ACTION 1 nurnber of operable Gross RadioacDyny Morutors channets less ODCM Note 1-ACTION 1 number of operab6e Gross RadcacDvey MonPors channets less than  !

Note 2-ACTION 2 continue release provided flow rate venfled ODCM Note 1-ACTION 2 conbnue release provided flow rate verrfied Note 2-ACTION 3 W!th no dilution water, Suspend radioactive hquid effluert ODCM Note 1-ACT10N 3 With no dilution water, Suspend radsoactive hquid emuent drschstges Attachment A 4 of 10 9/23/978-21 AM

Matrix of Changes / Relocations i Current PNPS Tecomical ag% u - .a.- - - a -

_-% 7 , . g +v' r ~~ ,a RADIOACTIVE GASEOUS EFFLUENT MONITORING ODCM Table 31-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING TABLE 3.8-2 INSTRUIENTATION INSTRUhENTATION Man Stack Emuent Morwtonng System ODCM T3.1-2.1 Man Stack Effluent Morwtonng Sie....

T3 8-2.1 Noble Gas Actfysy Morutor Provichng Alarm ODCM T3.1-2.1.a NotWe Gas Actrvey Morutor Providing Alarm T3 8-2.1.a T3 6-2.1 b lodine Sampier Cartndge ODCM T3.1-2.1 b lodne S W Caeev .

T3 8-21.c Partcuente Sampier Faer ODCM T3.1-2.1.c Particulate S nW Fdter Effluent System Flow Rate Measurmg Devce ODCM T3.1 -2.1.d Emuent System Flow Rate Messunng Device T3 8-2.1 d Sampler Flow Rate Messunng Devce ODCM T3.1-2.1 e SauW- Flow Rate Measunng Devce T3 8-21 e Reactor Building Venblation Effluent Morwtonng System ODCM T3.1-22 Reactor BuAL,s Ventilshon Emuent L' eis Sye.cn T3 8-2.2 Noble Gas Activey MorWtor Providing A! arm ODCM T3.1-22.a Noble Gas Activity Morwtor Providmg Alann T3 8-22 a T3 8-2 2 b lodme Sampler Cartndge CDCM T3.1-22D todine SanW Caeev .

T3 8-22 c Partculate Sampier Filter OOCM T3.1-2 2.c Parbculate SanW Faer Emuent System Flow Rate Measunng Devee ODCM T3,1 -2.2.d Effluent Sy e.u. Flow Rate Messunng Devee T3 8-2.2 d Sampier Flow Rate Messunng Devce ODCM T3.1-22 e S.n@ Flow Rate Messunng Devce T3 8-22 e Steam Jet Ar Ejector Radioactivity Morutor ODCM T3.1-2.3 Steam Jet Ar Encer Radioactrvey Morutor T3 8-2.3 Noble Gas Activity Morwtor (Providing Alarm and auto- ODCM T3.1-2.3 a NotAe Gas Actrvey MorWtor (Providog Alarm and auto-T3 8-2.3 a isolation of stack) isotebon of stack)

Augmented Offgas Treatment System Explostve Gas FSAR SA Gaseous Radweste S,_..

T3.8-2A Mon 6toring Hydrogen Monitor FSAR 9.4 Gaseous Radweste System T3.8-2.4.a Dunng releases via trus pathway ODCM T3.1-2 Note 2 Dunng releases vem ttus 4ay l T3 8-2 Note 1 During AOG system Operat6on FSAR SA Gaseous Radwaste S,-..

T3.8-2 Note 2 Dunng steam Jet air ejector operatson ODCM T3.1-2 Note 3 Dunng steam Jet air ejector operation T3 8-2 Note 3 cperable charriets < required gases may be released to ODCM T31-2 Note 1 @eble channels < requred gases may be released to T3 6-2 Note 4 the AOG provided ACTION 4 the AOG provided i

ACTION 1 operable channets < reqised continued release provided ODCM T3.1-2 Note 1 @ eble channels < requred conbnued release provided l T3 8-2 Note 4 flow rate a eshmated ACTION 3 flow rate is estimated ACTION 2 operable channels < requred contsnued release provided ODCM T31-2 Note 1 wbie channe's < requred conhnued release provided ,

T3 8-2 Note 4 grab samples are taken 1/12 hrs ACTION 1 grab samples are taken 1/12 hrs ACTION 3 T3.1-2 Note 1 operable channels < requred wia.Jed release provided l T3 8-2 Note 4 operable channets < requre6 conhnued release provided ODCM samples are contmuously coiiected ACTION 2 samp'es are continuously collected ACTION 4 FSAR g.4 Gaseous Radwaste Syem.

Note 4-ACT10N 6 operable channels < requered AOG operation may continue provided grab samples are collected Attachment A 5 of 10 9/23/978:21 AM

Matru of Changes / Relocations

~

Csstrent PNPS Tecimicas ; 2 - - : y4  % 7, - < - , a 2, , - _ Wyrp , w 4%. _,

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TABLE 4.8-1 RADIOACTNE LIQUID WASTE SAlWPLING AND ANALYSIS ODCM Table 4 t-1 RADf0ACTNE LIQUID WASTE SAIWPLING AND ANALYSIS PROGRAM PROGRAM T4 6-1 A Batch Waste Release Tanks ODCM T42-1.1 Batch Waste Releass Tanks T4 81.A.1 Non-Treatable Releases - ODCM T4 2-1.1.a Non-Treatable Releases T4 6-1 A 2 Treatable Releases ODCM T42-1.1 b Treatatwe Releases T4 6-1 B Continuous Releases ODCM T42-12 Conhnuous Releases T4 6-1 B.1 Salt Servce Water ODCM T42-1.2 a Salt Servce Water T4 8-1 Note = refer to ODCM ODCM T4 2-1 Noteo ' refer to ODCM et a cornposde sample is ODCM T42-1 Note"' a composte sampk es T4 8-1 Note ODCM 2 a batch mWase as T4 8-1 Note = a batch mkase is T42-1 Note T4 8-1 Note'a the pnncipal gamma emeters for ODCM T42-1 Note m the pnncipal gamma emeters for TABLE 4.8-2 RADIOACTNE LIQUID EFFLUENT MONITORING ODCM Table 4.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUENTATION SURVEILLANCE REQUIREENTS INSTRUMENTATION SURVEILLANCE REQUIREENTS T4 8-2.1 Gross Bets of Gamma Rad Mon # tors Provxting Atarm and ODCM T41-1.1 Gross Beta or Gamma Rad Monnors Providing Alarm and Automatic isolaten Automate isolaten T4 8-21 a Liquid Radwaste Effluents tJne ODCM T4.1-1.1.a Uquid Radwaste Effluents une T4 6-22 Flow Rate Measurement Devces ODCM T4.1-12 Flow Rate Measurement Devees T4 6-22 a uguid Radwaste Effluent une ODCM T4.1-12 a ugued Radwaste Effluent une 5 dunng or pnor to release vm this pathway ODCM T41-1 Note"' dunng or pnor to release we thes pathway T4 8-2 Note T4 8-2 Note 2 prevousy estateshed calibraten procedums ODCM T41-1 Note a pmveusy estat*shed calibraten procedums TABLE 4.8-3 RADIOACTNE GASEOUS WASTE SAMPLING AND ODCM Table 4.3-1 RADIOACTNE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ANALYSIS PROGRAM T4 8-3 Mar. Jtack annd Rx Bldg Vent ODCM T4 3-1 Main Stack annd Rx Badg. Vent refer to ODCM ODCM T4.3-1 Noe ,m refer to ODCM T4 8-3 Note '*'

T4 8-3 Note *' the pnncipal gamma emeters for ODCM T4 3-1 Note m the pnncipal gamraa ematers for ODCM T4 3-1 No*e tas when the average deity gross radioactivdy T4 8-3 Note m when the average daity gross radcactrvey T4 P W3 m d

the ratio of the sample flow rate to ODCM the rate of the samole flow rate to T4 8-3 Note'*

TABLE 4.8-4 RADIOACTIVE GASEOUS EFFLUENT NONITOR!NG ODCM Table 41-2 RADIOACTNE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE ItEQUIREENTS INSTRUENTATION SURVEILLANCE REQUIREENTS T4 8-41 Main Stack Emuent Morvtonng System ODCM T41-2.1 Man Stack Effluent Morwtonng System T4 6-41 a Noble Gas ActivityfAontor ODCM T4.1-2.1.a Noble Gas Activey Morutor T4 6-41 b todine Sampler Cartndge ODCM T4.1-2.1 b lodine Sampler Cartndge T4 6-41.c Partculate Sampler Filter ODCM T4.1-2.1.c Partculate Samp!er Fater T4 8-41 d Effluent System Flow Rate Measunng Devce ODCM T41-2.1.d Efbent System Flow Rate Measunng Devce T4 6-41 e Sampler Flow Rate Measunng Devee CDCM T4.1 -2.1.e Sampler Flow Rate Messunng Devee Attachment A 6 of 10 9/23/978:21 AM

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Matrix of Changes / Relocations Current PNPS Technical O __ -r- %

2 , e -

T4 8-4 2 Reactor Budding Vertitaten Emuent f corwtomg System ODCM T4.1-22 Reactor Buddog ventiaten Emuent Monitomg System T4 8-4 2 a Noble Gas Activey Monnor ODCM T41-22 a NetWe Gas Actwty Montor T4 6-4 2 b todine Sampler Cartndge CDCM T4.1-22b todene Sampler Cartndge T4 6-4 2 c Partculate Sampler Fdter ODCM T41-22.c Partculate Sampler Fater T4 8-4 2 d Emuent System Flow Rate Measunng Devce ODCM T41-22 d Emuent System Flow Rate Measunng Devce T4 8-4 2 e Sarnpler Flow Rate Measumg Devee ODCM T4.1-22.e Sampler Flow Rate Measunng Devce T4 8-4 3 Steam Jet Ar Ejector Radioactwty Monitor ODCM T41-2.3 Steam Jet At Elector Radcactway Montor T4 8 4 3 a Noble Gas Actwty Monitor ODCM T4.1-2.3 a NutAe Gas Actwry Montor T4.84.4 Augmented Offgais Treatment System Explosive Gas FSAR 9.4 Gaseous Radwaste System Monitoring T4.84.4.a Hydrogen Monstor FSAR 9A Gaseous Radwaste System Dunng rekases via ttws pathway ODCM T4.1-2 Note ' Dunng rewases via thrs v g-y T4 8-4 Note '

During AOG system Operation FSAR SA Gaseous Radwaste System T4.84 Note 2 S Dunng steam Jet ar ejector operaton ODCM T42-2 Note 3 Dumg steam jet at Wu operaten T4 8-4 Note ODCM 2 prevously estabirsted cahtvaton pmes T4 8-4 Note a previousty estatArshed calibraten procedures T4.1-2 Note a calibrate at 2 points with standard FSAR 9.4 Gaseous Radwaste System T4.84 Note Fsgu e 4 6-1 LgJed Radwaste Treatment System Schematic ODCM Fsgo 4 2-1 Liquid Radwaste Treatment SyWe SGs.ee figure 4 8-2 Gaseous Emuent Treatment Schemate ODCM Fsgure 4 3-1 Gaseous Emuent Treatmert Schemate MISCELt.ANEOUS RADIOACTIVE MATERIALS SOURCES FSAR 12A.1 Materlats Safety Program Use, Handhng, and Storage of 4.0 Licensed Radioactive Sources 4.* Scaled Source Contamination FSAR 4.2 Survestlance Requaterrents FSAR 4.3 Reports FSAR 4A Records Retention FSAR l

l l

l l

Attachment A 7 of 10 9/23/978:21 AM

Matrix of Changes / Relocations Current MFS TactudcL4 W + .A+ - sm G ;' iugt.%as x% #;;s- u m ,,,. W s$e p y w s:si -

6A MAJOR DESIGN FEATURES ITS 4.s DESIGN FEATURES See Features ITS 4.1 See Locahon 51 Reactor Core iTS 4.2 Reector Core 5.2 Reactor vessel FSAR 4.2 & App. M Reactor Wessel 6.3 5.4 Contamment 6.4.A Pnmary contaenmen. FSAR g.2.12 7 ? a prtmary contamment 5A.B Secondarycomnt #iment FSAR 6.3 * - .-y comntamment

~^

5.4.C Penetrations of pnmary contamenent FSAR g.2JA penetrahans of ,,_ _ _ y contamment Fue..'Jtorage ITS 4.3 Fuel Storage 55 new fuel storage faceny 4 ITS 4.3.12 a 8 b new hses storage faceny 4 55A 55B spent fuelpoot Q ITS 4.3.1.1.b spent Aset pool 4 5f C fuet assemtdy max K-infinpy ITS 4 3.1.1 a fuet assemby rnen K ." ;,

number of fuelassemphes stored ITS 43.3 number of fuelaseampnes stored 55D Loads m excess ITS 434a Loeds in excess 55E Fuel stored watun are ITS 4.3 4 b Fuel stored wahrt arc 55F FSAR 1.8.1.1.5, 2.5.3A,12.2.3.1.5. and ." m - -- C.

5.8 Seesmec Desegn 6 ADMNISTRATIVE CONTROLS ITS 5 ADMNISTRATIVE CONTROLS 61 Responsabehty ITS 5.1 Responstuity Stabon Drector ITS 5.1.1 Stabon Drector 6.1 ITS 5.12 Stuft Supennsor 62 Orgamzacon iTS 5.2 Organizaeon 6 2.A Onsae and Offene Orgaruzanons ITS S 2.1 Onsee and Offene Orge&shons 62B Urut Staff ITS 52.2 Una Staff 63 Urut Staf! Quahficabons ITS 5.3 Unit Staff Quahficahons 6.4 Traeneng FSAR 13.3 ~

6.5 Review and Audit FSAR 13A 6.5.A Operations Review Commettee (ORC) FSAR 13J.3 FSAR Change Respeest Required 6.C.B Nuclear Safety Review and Audit Committee (NSRAC) FSAR 13.3.5 FSAR CLnge Request Required 6.6 Reportable Event Action Reg 10CFR50.72/T3 Procedure 6.7 DELETED 68 Procedures .TS 5.4 Procedures 69 Reporting Requrements ITC 56 Reportng Requrements 6.9.A.1 Startup Report FSAR 13.6 REACTOR STARTUP AND POWER TEST PROGRAM 69A3 W""'"ml Exposure Tabulacon ITS S 6.1 %W Radiabon Exposure Report 69C2 Annual Radpological Erwronmental Monstonng Report [lTS 5.62 Annuel Radelogeat Erwironme ital Operahng Report Attachment A .

1 9/23/978:21 AM 8 of 10 2 I

l Matrix of Changes / Relocations Current PNPS Tectmecal Specsftcations 69C1 Sens-Annual Radcactrve Emuent Release Report ITS 56.3 Radoactue Ef!!uere Releaso ?teport 69A2 Monthly Operatog Report ITS 5.64 More# Operating Reports 69A4 Core Operstmg Limits Report ITS 5.6.5 Core Operating Limits Report (COLR)

Ts.9 1.a Secondary Contaenment Leak Rate Testmg to CFR Se, Appendix J and te CFR 84.73 S.10 Record Retention FSAR 13.7.5 (Identicalto CTS) 6.11 Radiation Protection Psograrn FSAR 13.6.5 6.12 DELETED 613 Hsgh Radiaten Area ITS 5.7 High Radiation Area ITS 5.5 Prograrns and Manuals ITS 5.52 Primary Cociant Sources Outside Contamment ITS S 5.3 Post Acendent Sampimg

!TS 5.5.4 Radcactive Emuent Controh Progwn ITS 5.55 Component Cyctic or Transient Limit ITS 5.56 Techncal SW -,.. (TS) Bases Control Program 7/S.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7/s.1 Monstormg Program ODCM 3/4.5.1 Monitoring Prograrn 7.1. A Conduct Envronmental Morntonng Program ODCM 35.1 Conduct Erwronmental Morwtonng Program 7.1.A 1 Program not bemg conducted ODCM 3 51.a Program not bemg conducted 7.1.A.2 Radcactwity exceeds reporting level ODCM 3.5.1.b Radcactwsty exceeds reporting level 7.1 A 3 Milk and Leafy vegetab6e Samples unavadable ODCM 3.5.1.c Milk and Leafy vegetable Samples unavadable 81A determine cumulatwe dose contnbutens ODCM 4.5.1 determme cumulatue dose corenbutens 7/81 B Land Use sensus ODCM 3/452 Land Use sensus 7.1 B Conduct Land Use sensus ODCM 3.52 Conduct Land Use einsus 7.1 B Acton 1 Cornmrtted dose > vasues calculated ODCM 3 5.2 Acton a Cornmitted dose > values calculated 7.1 B Acton 2 Commeted dose 20% > values calculated ODCM 3 5 2 Action b Commeed dose 20% > values calculated 81B Conduct land use census ODCM 45.2 Conduct land use census 7/8.2 Dose - Liquids ODCM 3/4.2.2 Dose -Lkgueds 72A Dose wum umnt to member of pubhc ODCM 322 Dose comfrutment to member of putte Report ODCM 3.22 Action Report 7.2 A. Acton 8 2.A Determme cumutatue dose contnbuten ODCM 422 Determine cumulatwe dose contnbuton 3/43.2 Dose - Notple Gases 7/5.3 Dose - Noble Gases ODCM 7.3 A Air dose 1:mits ODCM 3.32 Ar dose famits Report ODCM 3.32 Action Report 7 3 A Acton Determme cumulatue dose contnbution ODCM 4.32 Determine cumulatwe dose contnbution 83A Attachment A 9 of 10 9/23/97821 A.A

(

Matrix of Changes / Relocations Current PHPS Taah=a a ep.,an aa _

, . - . jp ygg x .g . 1c x sg3, m ;qq. , w3 , s ,

7/8.4 8-131. 5-133. RasJ Maternal in Particueste Form & Trttsum ODCM 3/4.3.3 3-131. 5-133. Rad Maternal tre Partarnd se Form & Trstissu Dose to member of pubic ODCM 3.3.3 Dose to member of pleic 74A Repmt ODCM 3.3.3 Acton Report 7.4 A Action 84A Determme cumulatwe dose contnounon ODCM 4.3.3 h *- currralstive dose contreubon Total Dose ODCM 3/4.4.1 Totat Doce 7/8.5 Dose w....dtmert to member of pubhc ODCM 341 Dose ccmtrwtrnert to member of pubhc 75A Report -ODCM 3 41 Adion Report 7.5.A Actson Determme cumulatue dose contrixJton ODCM 441 Determne cumulatwe dose contnbubon 85A Regertmg Levels for Radsoactive Concentrations Reporting Levels for Radeosctive Concentrations tri Emeroame tal ODCM Table 3.5-4 Samples Operami Radsologscal Environmental Monitormg ODCM Table 3.5-1 Operatsonal RJ-~.f .i Environmental Monstoring T.,.arn Table 8.1-1 Prograrn .

gross Beta rascacDvey > 10 ames control value ODCM .251 Now'4 groes Beta radcactMty > 10 ames contml vabe T81-1 Note 1 T81-1 Note 2 gamma esotope means ODCM T3 5-1 Note *** gamma -,~ --

mtegrated gamma actwey > 10 times control value ODCM T3 5-1 Note *' = ewe4 gamma acc: W > 10 ames control veaue T81-1 Note 3 edcates controllocaten ODCM T251 Note '2' Indicates controllocanon T8.1-1 Note 4 fish anatysts we be performed on a minimum ODCM T3 5-1 Note

  • Ash e4-- we be g-ne on a n-a T81-1 Note 5 T81-1 Note 6 musset samples from four locatens ODCM T351 Notet mussei- @ from four locations TB 1-1 Note 7 sedimert samples from four locatens ODCM T351 Note
  • sue nW from fourlocatens these locations may be atered ODCM T3 5-1 Note
  • these locanors may be aftered T81-1 Note 8 T81-1 Note 9 rrurumum senstwees for gamma exposure ODCM T3 5-1 Note m rrJnsmum senstwibes for gamma exposure Aer Particulate Gaseous Radiodme and Soil ODCM Table 3.5-3 Air Parti s itsee Gaseous Redsorkee and Soil Surveillance Table 8.1-2 Survedlance Stations Stations External Gamma Surveellance Stations ODCM Table 3.5-2 EnvironmentN TLD Locations Table 8.1-3 Deleted Notes act reg *ed T81-3 Note
  • Themiummescert do*.mters (TLDs) 2 Contml StatrM Oeleted Notes not q_ J T81-3 Note T81-3 Note 3 TLDs for thrs locaten we be pmvided peasted Notes Cw 4 Table 8.1-4 Mmsmum Values for the Lower Limsts of Detection ODCM Taele 4.5-1 Detection C rabilities for Emironmental* .m A. , .;.

Lower Limit of Detection (LLD)

T81-4 Note

  • Refer to ODCM ODCM T4 5-1 Note A Refer to ODCM W LLD for Surface water T8-1-4 Note LLD for Surface watr ODCM T4 5-1 Not3 LLD for leafy vege*C ODCM T4 5-1 Note ## LLD for leafy vegetabees T8-1-4 Note
  • If no dnnfung water y %y ODCE T4 5-1 Note # If no dnn',ing wa%r pothway TB-1-4 Note "

Attachment A 10 of 10 9/23/97821 AM I l

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