ML20006B533

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Radiation Protection & Radiological Environ Monitoring
ML20006B533
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 01/24/1990
From:
Public Service Enterprise Group
To:
Shared Package
ML20006B528 List:
References
NUDOCS 9002050036
Download: ML20006B533 (36)
v • d • e


Text

{{#Wiki_filter:..... TABLE 3.12.1-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIR0000 ENTAL-SAMPLES: 9 REPORTING LEVELS m. - Water-Airborne Particulate Fish . Milk' Food P W ts 3 Analysis (pci/t) or' Gases (pCi/m ) (pCi/kg, wet) (pci/t).

(pCi/kg, wet)-

H-3 30,000 Mn-54 1,000 30,000 %o Fe-59 400 10,000 @'d J 88 Co-58 1,000 30,000 - n o-- og Co-60 300 10,000 'i ono w oN Zn-65 300 20,000 0 . $0$ U '400 J Og 4 Zr-Nb-95. I-131 0.9 3 - 100-Cs-134' 30-10 1,000 -60 1,000 Cs-137 50 20 z2,000 70; 2,000

Ba-La-140 200 300 1

N ?b : ES W $0 CYS SATS. ~ llll. Ykfuf ff y hyy Y kr' ' kr> Kr 4)Cther ' W f S s a lu e A go yC;/A n y bf ,,,,f pdway

egrsts,

~ g .1 hw ,.sc-am eshssi_ muss.*--+-.,%,-aee-s-#A-d==-==wh.m4w w_s w .-(-%e.w-mm_, v,.- .wh,:<wua--.m.- - -. --*-.--.m J.,..-.-mu- _m w m-- wp-

=1"m. 6,, TABLE 4.12.1-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (1)(2) k . LOWER LIMIT-0F DETECTION-(LLD)(3) E Water

Airborne Particulate Fish'

- Milk Food Products Sediment Analysis (pCi/f) or Gas (pCi/m ) -(pCi/kg, wet). (pCi/f) (pCi/kg, wet) (pCi/kg dry) 3 gross beta 4 0 01 H-3 3000 4 Mn-54 15 130 Fe-59 '30 260 Co-58,60-15 130 R Zn-65 .30 260 0 d, Zr-Nb-95 15 o I-131

1

'O.07 1 60" Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06-150 18 80 180 Ba-La-140 '15 15 r t.to Gr drinatop " W sadPk s. rF no dr:nn:og akt pad.ug c,;gQ a va/g, nofQ/t #1 be used. k lf n.. c. - :.. -... ~,

i f .l y y ~ TABLE 4.12.1-1 (Continued) TABLE NOTATIONS ) -(1)This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable,_together with those of the abcve.- nuclides,'shall also be analyzed and reported in.the Annual-Radiological Environmental Operating Report pursuant to Specification 6.9 1.6. (2) Required detection capabilities for thermoluminescent dosimeters used-for environmental-measurements shall be in accordance with the recommendations i of Regulatory Guide 4.13. j (3)The LLD is defined, for purposes af these specifications, as the smallest-concentration of radioactive material in a sample that will yield:a net-count, above system background,.that will be-detected with 95% probability with only 5% probability of falsely conclu61ng that a blank observation represents a "reat" signal. For a particular measurement system, which may include radiochemical separatton: 4.66 s D LLD = - 'E V 2.22 exp(-Aat) .Y Where: LLD is the "a priori" lower limit of detection as defined above - as picocuries per unit mass or volume, ss is the standard deviation of the background counting rate or of 4 l the counting rate of a blank sample as appropriate, as counts per [

minute, E is the counting efficiency, as counts per disintegration, l

i l V is the sample size in units of mass or volume, 2.22 is the-number of disintegrations per minute per picocurie, Y is the fractional. radiochemical. yield, when appiicable, A is the radioactive decay constant for the particular'radionuclide ,sec 1), and .j ( at for environmental-samples is the elapsed time between sample collection, or end of the sample' col ~lection period, and: time of' counting (sec) Typical valves of E, V, Y, and At should'be used-in the calculation. .y ( HOPE CREEK 3/4 12-11 { -i

r n m 1: .a:: 5; ~% INDEX. ? -} ADMINISTRATIVE-CONTROLS d 4 j SECTION i PAGE 6.1' RESPONSIBILITY.................-.......... 6. 6.2 ORGANIZATION.............................................'....... 6-1 i 4 6.2.1 ONSIi E AND OFFSITE ORGANIZATIONS.......:................... 6-1 6.2.2 UNIT STAFF.................................................. 6-l' Figure 6.2.1-1 (Deleted)................................ 6-3 ll Figure 6.2.2-1 (Deleted)................................ 6-4 l Figure 6.2.2-2 Minimus Shift Crew Composition-1 Single Unit Facility..................... 6-5 6.2.3 SHIFT TECHNICAL ADVIS0R................................... 6-6 6.3 UNIT STAFF-QUALIFICATIONS...................................... 6-6' i

6. 4 TRAINING.......................................................

5-6 1 i e

6. 5 REVIEW AND AU0IT.....................P..................'........

6-6 l ~ 6.5.1 STATION OPERATIONS REVIEW COMMITTEE(S0RC)................. 6-6 =l l FUNCTION................................................. 6-6 COMPOSITION.............................................. 6-7 \\ i ALTERNATES................................................. 6-7 MEETING FREQUENCY........................................ 6-7 t QU0 RUM................................................... 6 1 RESPONSIBILITIES......................................... 6-7 REVIEW PR0 CESS............................................ 6-8 l 1 AUTHORITY..,............................................... 6-9 RECORDS. M.4. M R 9%TM........................... A 6-9 HOPE CREEK xxiv - Amendment No. 21 I l.. r k

_s -h INDEX~ ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUCLEAR SAFETY REVIEWHN6344 d.@ M.Q.l.T............... 6 ' A FUNCTION................................................... 6-9 COMPOSITION................................................ 6-9; CONSULTANTS............................................... 6-10 0FFSITE SAFETY REVIEW (0SR)..........................-...... 6-10' FUNCTION.................................................. 6 REVIEW.................................................... 6-10 AUDITS.................................................... 6.11 R E CO RD S / N.4.. M.@.M.............................. 6-12 ONSITE SAFETY REVIEW GR0VP (SRG).......................... 6-12 > Fu M c.Ti o u,,,,...,,....................,...... (. - 12. RESP 0NSIBILITIES....................'...................... 6-12 AUTH0RITY................................................. 6-13 6.5.3 TECHNICAL. REVIEW AND CONTR0L............................... 6-13 ACTIVITIES................................................ 6-13' PROCEDURE RELATED DOCUMENTS............................... 6-13 NON-PROCEDURE RELATED DOCUMENTS........................... 6-14 R ECO RDS dN Q.MP.QO................................. 6 j 6.6 REPORTABLE EVENT ACTI0N........................................ '6-14' '6. 7 S AFETY LIMIT VIOLATION......................................... 6 ' 6.8 PROCEDURES AND PR0 GRAMS........................................ 6-15 l L 6.9 REPORTING REQUIREMENTS.......................................... 6 'i 9 6.9.1 ROUT I N E R E P 0 RTS........................................... 6-17 STARTUP REP 0RT............................................ 6.17 l l L i i HOPE CREEK xxv I

INDEX ADMINISTRATIVE CONTROLS' i SECTION PAGE ANNUAL REP 0RTS............................................ 6-17 ANNUAL _ RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.'....... 6-18 SEMIANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.... 6-19 MO NTH LY O P E RAT I NG R E P0 RT S................................. 6-20' j 6.9.2 SPECIAL REPOR1S.~...........................-............... 6-20 6.10 RECORD RETENTION.............................................. 6-21 6.11 RADIATION PROTECTION PR0 GRAM.................................. 6-22 s 6.12 HIGH RADIATION AREA...........................................-'6-22 6.13 ' PROCESS CONTROL PROGRAM (PCP)................................. 6-23 5 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)........................ 6-24 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS................................. 6-24 t -l l l i 1 -f -l ) i i i

l HOPE CREEK xxvi L

I 1

4 ? / 1 3 e ~! ~i \\; f i I 'i '.j' I s SECTION._6.0 ADMINISTRATIVE CONTROLS- 'I 1 i

i l

i 'l 4 i t 1 l 4 L .i 1 i 6 l l. i !'j s I ,-j A

j 6.0- ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 'The General Manager - Hope Creek Operations shall be responsible for I' overall unit operation.and shall delegate in writing the succession to this. .respon'ibility during his. absence. H s s 6.~ 1. 2 The Senior Nuclear Shi.f t Supervisor'or-during his. absence from the' control room, a designated individual shall be responsible for-the control: room command function. A management directive-to this effect, signed by the H Vice President and Chief. Nuclear Officer shall be reissued to all station ] 1 personnel on an annual basis. 6.2 ORGANIZATION 6.2.1 ONSITC AND OFFSITE ORGANIZATIONS' Onsite and offsite organizations shall'be established for unit' operation:and i corporate management, respectively..The onsite and offsite organizations shall include positions for activities affecting the sGfety of the nuclear power ~

plant, a.

Lines of authority, responsibility, and communication shal1 be - ~ established and defined from the highest management levels through. intermediate levels to and including all' operating organization positions. These relationships shall.be documented and updated,.as appropriate in the form of organization. charts - functional descrip-tions of departmental responsibilities and relationships, and job descriptions for key personnel' positions,'.or;in equivalent forms t of documentation. These requirements'shall be documented in the-l Hope Creek Generating Station. Updated Final Safety' Analysis Report and updated in accordance with 10' CFR 50.71(e). b. The General Manager - Hope Creek Operations 1shall-be responsible for overall. unit safe operation and.shall ~have control over tnose onsite activities necessary for safe operation and maintenance.of the plant, The Vice President and Chief Nuclear Officer shall have corporate ~ c. responsibi.lity for overall plant.' nuclear safety and shall'.take any. measures needed to ensure > acceptable performance:of.the staff in operating, maintaining, and providing technical: support to the plant' to ensure nuclear safety. L d. The individuals who train the operating staff and those who' carry: + out health physics and quality assurance functions may report to the-appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their. independence from operating pressures. UNIT STAFF' 6.2.2 The unit o'rganization shall be subject to the following: Each on duty shift shall be-composed of at least the minimum shift a. crew composition shown in Table 6.2.2-1; i -i HOPE CREEK 6-1 Amendment No. 21

,cf ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b. At least one licensed Recctor Operator shall.be in.the control room when fuel is in the reactor. In _ addition, while the unit is-in OPERATIONA' CONDITION 1, 2 or 3, at least one licensed Senior.- .Reacter Operator shall be in the control room; ^ i f t ti r * @ :ti n T -,.. m m r M = :it tr 'r' i N WJ \\ ALL CORE ALTERATIONS shall be observed and directly: supervised by? either a licensed Senior Reactor Operator or licensed-Senior Reactor' i Operator Limited' to Fuel' Handling who has: no other' concurrent respon-sibilities during this operation; and' d/ Administrative procedures shall be developed-and implemented to~ limit-the working hours of unit' staff who rerform safety-related functions. e.g., licensed Senior Reactor Operators, licensed Reactor. Operators, radiation protection technicians,. equipment operators, and, key main-tenance personnel. K8/. Operations ~ nager, Oper ing Engineeh Senior Nuc at Shift-Sup visors, Nucl r Shift-Sup visors, and enior Opera 'ng Super-visor all hold a nior reacto operator.li nse. The lear L Control erators sha hold a rea.or operato license. V Adeq,uate shift coverage shall be mainta,ined without routi.no-heavy l use of over-time. The objective shall be to have operating personnel work a normal 8'-hour day, 40-hour week while the unit is operating. - However, in the event that- < unforeseen problems require sub'stantial' amounts of overtime to. be -used,: or-during extended periods of shutdown for refueling, major maintenance on major unit modifications, on a temporary basis the following guidelines shall be' followed: i 1. An individual should not be permitted to work-more -than 16 hours straight, excluding shift turnover time. 1 2. An individual should not be permitted to work more than 16 hours in any 24-hour period, not more than 24 hours in any 48-hour period, _nor. more than 72 hours in any 7 day period,'all excluding. shift turnover time.- 3. A break of at least 8 hours should 'be allowed between work periods, including shift turnover time. 4. Except during extended shutdown periods, the use of overtime should be-r considered on an individual basis and not for the entire staff on a shift. Any deviation from the above guidelines shall be authorized by the appropriate department manager, or higher levels of management, in accordance with estab-l lished procedures and with documentation of the basis for granting the devia-: ? tion. Controls shall be included in the procedures such that individual over-time shall be reviewed monthly by. the General Manager-Hope. Creek-Operations or his designee to. assure that excessive hours-have not beeniassigned. Routine-deviation from the above guidelines.is not authorized. n "The Radi n' Protection Technician e unavailable for a peri f time E not exceed 2 hours, in order accommodate unexpected-ab e, provided i diate action is taken

  1. 1 the required Dosition.

HOPE CREEK 6-2 Amendment No. 21 .i 4 I e + e w .,.n.,,na. . ~..,. ~,,,,,.,., .,r, w a-k

1,. .l 1 1 i - i,

)

-i 'I .i e >.} i I m. .t t ,e mw e, wa Ww-1 a '3* .i o -w 1 3 i r 1 'l. -i -I I HOPE CREEK 6-3 - Amendment No. 21 -q l ~ > b I 4 y .j

.....iii.a. ..i..ii.,,ii.ii.2.

..,gt.. -,.

f P c .) I t' i .i 'l ,1 r -i . N. g3 ; j w'. n: ,,i 4 w . ew. W ww- @ CD-1 8 .-. i - w i si . i, \\ J - 1 1 i i s ' 1 i ( .I i . HOPE CREEK 6-4 Amendment No. 21 i se / . _............. _ _..... =

5 j ? i TABLE 6.2.2-1 i ~ MINIMUM SHIFT CREW COMPOSITION ' SINGLE UNIT FACILITY l POSITION NUMBER OF' INDIVIDUALS REQUIRED TO FILL POSITION. 1 CONDITION 1. 2. or 3 CONDITION 4 or 5 f SNSS* 1 1 NSS* 1 None NC0 2-1 E0 2 1 RP1 yTA {(1 N one l .i TABLE NOTATION : SNSS - Senior Nuclear Shift Supervisor with a Senior Reactor Operator license on the Unit NSS - Nuclear Shift Supervisor with a Senior Reactor Operator license o on the Unit l NCO - Nuclear Control Operator with a Reactor Operator _ license on the Unit EO - Equipment Operator i .STA - Shift Technical Advisor 17T" '%diation Prtrhtctic8er.hMc. inn Except for the Senior Nuclear Shift Supervisor, the. shift crew compcsition may be one less than the minimum requirements of Table 6.2.R-1 for a period of time not to exceed 2 hours in order to accommodate unexpectts absence of on-duty shift i crew members provided immediate actioncis taken to restore the shift crew compo-sition to within the minimum requirements, of Table 6.2.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to.an -{ ' oncoming shift crewman being late or absent. [_ During any absence of.the Senior Nuclear Shift Supervisor.from the control room while the unit is in OPERATIONAL CONDITION 1, 2 or 3, an individual with a. valid Senior Reactor Operator license shall._be designated.to assume the control room command function, During any absence of the Senior Nuclear Shift Supervisor from the control' room while.the unit is in OPERATIONAL CONDITION 4 or 5, an individual with'a valid-Senior Reactor Operator license or Operator license i shall.be designated to assume the control room command function.. p L "In cases where an individual has=a Seier Reactor Operator's license on the unit, is a qualified STA, and has a Professional Engineers License by virtue y of successful completion of the Professional Engineers examination or.a ~: bachelor's' degree in a scientific, engineering, or engineering technology discipline from an accredited institution, the individual.can serve in a dual 1 o _ role capacity-.as either the SNSS/STA or_NSS/STA. (Note: For those individuals F with a bachelor's: degree in a scientific or engineering technology discipline, . course work must have included physical', mathematical,-or engineering science;) i. Otherwise, there shall'be a qualified STA as well as a.SNSS and NSS on-shift.- t f HOPE CREEK- '6 ' I f

'a J N 3 F X V (o. 5. 2 Aid G.*5.L The operations manager, operatine Engineer, senter Nuclear $hift .mdaas shall [ hold a senior reactor opeMtor license. Supervisors, Nucle 2;;: - The Nuclear Control.0perators shall hold a reactor operater license. ,l q ~

ADMINISTRATIVE CONTROLS 6.2.3 SHIFT TECHNICAL ADVISOR 6.2.3.1 The Shift Technical Advisor shall provide advisory technical support to the Senior Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room. in8Widual d4Si nam as M 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimym1 qualifica- . tions of ANSI /ANS 3.1-1981 for comparable positions, except for thdYadiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Reactor Operators and Senior Reactor Operators shall also meet or exceed the minimum qualifications of the supple-mental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licansaan-4 i 76J SE.T.T G., 3.1 } 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager-Nuclear Training, shall meet or exceed the reaJirements and recommendations of Section 5.5 of ANSI /ANS 3.1-19f;l i I gnAppend"x 10 CFR Part 55Iand the suppl al requiremen ecified in Sections d C of Enclosur of the Mar , 1980 NRC le to all licen-sees d shall include iliarizatio th relevant in ry operational rience.g 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Site Protection and shall meet or exceed the require-ments of the SRP (NUREG-0800) Section 13.2.2.11.6, 10 CFR 50 Appendix R and Branch Technical Position CMEB 9.5.1, Section C.3.d. 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE (50RC) _ FUNCTION i 6.5.1.1 The 50RC shall function to advise the General Manager - Hope Creek Operations on all matters related to nuclear safety. HOPE CREEK 6-6 1

l ADMINISTRATIVE CONTROLS COMPOSITION pb gwg

6. 5.1. 2 The 50RC shall be composed of the:

7 Chairma neral Manager - 4 Nope Creek Operat r and Vice irman: Operations Mana r ar#d Vi Chairman: Technical Man r er: Maintenanc nager Member: I&CE r Member-Syst ngineer Memb : Radt ion PMtection/Chemis name - r: asist'on Protection E neer or Chemistry Engineer Member: Onsite safety Revi Engineer (or designee) ALTERNATES 6.5.1.3 All alternate membe shall be appointed i riting by the 50RC Chairman. a. Vice Chairne all be member,s of Sta on management. b. -No more t two alternates to es shall participate a oting l member n 50RC ac'tivities at a one meeting. c. Alt ate appointees will o represent their respe ve artment. d. Alternates for members 11 not make up part o. he voting quorum when the member the tornate represents is so present. j MEETING FREQUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convened by the 50RC Chairman or his designated alternate. QUORUM 6.5.1.5 The quorum of the 50RC necessary for the performance of the 50RC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four members including alternates. A gg g3 g( RESPONSIBILITIES t 6.5.1.6 The 50RC shall be responsible for: a. Review of: (1) all Station Administrative Procedures and changes thereto and (2) Newly created procedures or changes to existing. t HOPE CREEK 6-7 }, ...v.,_. ..J

l i INSEF.T To SECTION 6.5.'1.2 chairman: General - Manager- - Hop Or~cEk Operations-1 Member and'Vice chairman: Maintenance Manager 3 Member and vice chairman: Operations Manager j Member and Vice. Chairman: Technical' Manager-1 Member . Radiation Protection / chemistry. Manager Member: Radiation-Protection Engineer Member chemistry Engineer l Member: Maintenance Engineers Members operating Engineers Member Technical Engineers (Group Heads) Member: Onsite Safety Review Engineer I I t INSERT TO SECTION 6.5.1.3 t 6.5.1.3 Alternates: a. Alternates shall.be appointed by the 80RC Chairman in writing. I b. Only4 designated vice chai may.act'as chairaan of a-SoRC meeting in the absence of the General Manager - Hope OrcekOPerations. The Senior Nuclear Shift Supervisor'(SNSS)-may act as-c. an alternate-for the Operations Manager-or an operating Engineer. The SNSS may also act as an~ alternate When ) the Operations Manager is acting ~as chairman O i n n l i l V i = - - - - - - - - - - - - ~ ~ ~ * "

- t, i 4 e l l j. i I ) l I 'k 6 INSERT To SECTION 4.5.'1.5 N a. We more then two seabers or one seaber and one alternate free any individual department wall.make up part of the veging quorum. No more. than 'eng, Operding En$lner and one.Teshnicat hinser m=+ be,part af tho gueturn. E b. If the Chairman for a meeting ie.a Vice Chairaana.then i up to two additional membere (or'ene member.and one . alternate) may be part of the voting;querus. 3 f 4 l i i e h

    • e s s.

4 4 l sti i l

I

-m i 1 L .w . -, -. -...., +. .--4_.--.,,... m.. m m m -.. 2 m

l ADMINISTRATIVE CONTROLS t procedures thatl..... e. ;;'7t;;;t ;;f;'. i.__ as described in l Section 6.5.3.2.d. Q,4, g c,p g, g g g,y g g g b. Review of.all proposed tests and experiments that affect nuclear safety. Review of all proposed changes to Appendix "A" Technical Specifications, i c. d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. e. Review of the safety evaluations that have been completed under the orovisions of 10 CFR 50.59. t 'Enitiertion ot rtview et ] v

f. +/nvestillatf orgof all violations 'of thdTechnical Specifications includ-i ing the ;r:- r;;::: ;;; ";r.;. :;r.;,' reprirts coverina evaltations F

_ and recommendations to prevent recurrence '- "- "'- "---'---' ---' ~ 'i i IMut! - " !::r :rf t the C: : :! ":::::r "::1:07 S:f:t; "-';f r_. I i g. Review of all REPORTABLE EVENTS. I h. Review of facility operations to det'ect potential nuclear safety hazards. g 1. Performanegorspecialreviews,investicationsoranalysesandreports N'0". *d "?". "".'*_"_". __E" "" 5..b[ 3 2 = __a _ _........ ~. j. Review of the Facility Security' Plan and implementing procedures and m s M P crrit r;::--: ::: :N::::: t: it :::rd "rr'::--] i hitt; "r;ir3 or evolve a petsettial eBace 4be,ega'c.+ivict35 r ReviewoftheFacNthEhd$ncy$thna$dYmo~1emen n6 procedures _and k. g g.}hggy,

.;;.;' ; ;.;,;; ^, re; - _ 2 ; ;;;r.;;_ t; t%. ;;_7d "; ---

"" :!:;r I 5: f: t'. ".:';i r_^J 3 oc 1melft.G. PotsMio.l in 4he, g4fsseive.ns.FF of .tha{ bunre. %s plan on-to cpt gio saftAy e.valuahon _,ReviewoftheFireProtdctionPrograma. 1 n ementing procedures and o,10 CFR 50.59 [2.;f.a;d;' d ~ ~ ~ ~ ~~~~ ~ -- --~~~~ ' ' ' Review of all unplanned on-site releases.of-radioactivity to the-m. environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action t) provent recurronceI:r tt Sn:rtin; ;f tr.;n, g;r ;; te ;;. Vi;; 're. ;.c.'. I 1-

d Oh':f ";;i;.7 Offf;;r ;.4 te th; 0..;rel ";rz::7-' ".;1; a 8

L Oef.'e "_r:irc. fg n. Review of changes to the PROCESS CONTROL MANUAL and the OFF-SITE 0055 CALCULATION MANUA!;, ;;d th; " r;;;;. Tre;'n.A 0.1_ 1 i-REVIEW PROCESSS 6.5.1.7 A technical review and control system utilizing qualified reviewers 'I shall function to perform.the periodic *or routine review of procedures and changes thereto. Details of this technical review process are 'provided in-Section 6.5.3. l i HOPE CREEK 6-8 . Amendment No. - 21 'f. e

i e 1 ADMINISTRATIVE CONTROLS 1 AUTHORITY

6. 5.1. 8 The 50RC shall:

Praik reamm.aam I i j Iamaannandlin writing to the General Manager - Hope Creek Operations a. [',nficer%)-.+ approval or dsaooroval of. items considered under Specifica-I tion 6.5.1.61 L..:..grior to their implementation, b. Provide written notification within 24 hours to the Vice President &ati+ Assornau7 and Chief Nuclear Officer and to the General Manager -:" c': -' ^. _, _. u_?of disagreement between the 50RC and the General andN00 k j _ Manager - Hope Creek Operations; however, the General Manager - Hope Creek Operations shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1. i RECORDS AMD REPORT 5 O ns

6. 5.1. 9 The.50RC shall maintain es of each SORC neeting, and copies shall be provided to the Vice President --- --

' General Manaaer - l 'snd Manager -f2-2 2: 12 :t- ":-- ' : Muclear-S=Q.4 y_ N.

6. 8. 2 NUCLEAR SAFETY REVIEW ANb Aubir' S

FUNCTION e i 6.5.2.1 The Nuclear SafetyliinIDepartment;m";'shall function to provide the independent safety review progiam and audit of designated activities. 1 COMP 0SITION [ ySEET" .1, 6.5.2.2 NSR shal onsist of the General ager - Nuclear Safety ow,.the i Manager - Off ' e Safety Review, who i upported by at least fo dedicated, full-time inears, and the Onsit afety Review Group, whi s managed by 4 the 0 e Safety Review Engin and is supported by at st three dedicated, f time engineers located site. 1 Nuc. lear Safe +y ansi 4ha./ The Manager 40ffsite Safety Review cations described in Section 4.7 of ANS Jtarr shall meet or exceed the qualifi- .1 - 1981 and shall be guided by the-l provisions for independent review described in Section 4.3 of ANSI N18.7 - l 1976 (ANS 3.2). The Offsite Safety Review staff shall generally ' ossess experience and p j competence in the areas listed in Section 6.5.2.4.1. A system of-qualifiec-- reviewers from other technical organizations shall be utilized to augment *M M ', expertise in the disciplines of Section 6.5.2.4.1, where appropriate. Such qualified reviewers shall meet the same qualification requirement as the Offsite Safety Review staff, and shall not have been involved witn performance 3 of the original work. [ Groopj The Onsite Safety Review;;nd = :2 3 staff shall meet or exceed the qualifica-tions described in Section 4.4 of ANS 3.1 - 1981. 1 HOPE CREEK 6-9 Amendment No. 21 I Mr, . ~..

1 l i i l. \\ I i l l .i 'i INSERT 1 TO SECTION 6.5.2 i w i COMPOSITION 6.5.2.2-The Nuclear Safety Dapartment, under the cognizance'of. i the General Manager - Quality Assurance and Nuclear Safety, shall. Review staff (CSR) consist of the Manager - Nuclear Safety, the.Offsite Safety and the Onsite Safety Review Group (SRG).' OSR statf and'the SRG each consist of-at least four dedicated,The full-time engineers. i l l l o O l

t ADMINISTRATIVE CONTROLS CONSULTANT $ g gjpgjegg-M y De.pm M ant GS M 6.5.2.3 Consultants or other technical experts shall be utilized-by = the M

===========:========-=,=-u

=% 6.5.2.4 0FFSITE SAFETY REVIEW (0$R) FUNCTION g ? 6.5.2.4.1 The 05R shall function to provide independent review and audit of designated activities in the areas of: a. Nuclear power plant operations, b. Nuclear engineering, c. Chemistry and radiocnemistry, , d. Metallurgy, e. Instrumentation and control.. f. Radiological safety, 4 g. Mechanical engineering, , h. Electrical engineering i. Quality. assurance l j. Nondestructive testing k. Emergency preparedness k ,M REVIEW 6.5.2.4.2 The 05R hall review: a. The safety evaluations for changes to procedures, equipment, or systems; and tests or experiments completed under the prevision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; b. Proposed changes to procedures, equipment, or systans and tests or experiments which involve an unreviewed safety question as defined l in 10 CFR 50.59; c. Proposed changes to Technical Specifications or this Operating License; d. yfolations of. codes, regulations, orders, Technical Specifications, l license requirements, or of internal procedures or instructions having v nuclear safety significance; e. Significant operating abnormalities or deviations free normal and expected performance of facility equipment that affect nuclear safety; H0PE CREEK 6-10 1. .-.n----

f I, o ADMINISTRATIVE CONTROLS L f. All REPORTABLE EVENTS. g. All recognized indications of an unanticipa,ted deficiency in some aspect of design or operation of structures, systems, or components-1 that could affect nuclear safety; and -j h. Reports and meeting minutes of the'SORC. AUDITS 6.5.2.4.3 Audits of facility activities shall be performed under the cogniz'nce, I a of the 05 Theso audits shall encompass: MOW a. Iie. conormance of facility operation to provisions contained within the Technical Specifications and applicable' license conditions at least once per 12 months; t b. The performance, training and qualifications of the entire facility 1 staff at least once per 12. months; The results of actions taken to. correct deficiencies occurring in c. 1 facility equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d. The perfor'mance of activities required by the Operational Ouality ' Assurance Program to. meet the criteria of' Appendix B 10 CFR Part 50, i; l at least once per 24 months; i e. The Facility Emergency Plan and implementing procedures at least once per 12 months; f. The Facility Security Plan and implementing procedures at least once ~ 6 per 12 months; i g. Any other area of facility operation considered appropriate by the' General Manager -I""-'-- ""^ " ~- "or the Vice President and Chief Nuclear Officer;g g g g g ggg l h. The facility Fire Protection Program'and the. implementing procedures at least once per 24 months; i. The fire protection and loss prevention program implementation at least once per 12 months utilizing either a-qualified off-site licensee fi.re protection engineer (s) or an outside' independent fire protection consultant..An'outside independent fire' protection; con-i sultant shall be utilized at least once per 36 months; and j. The radiological environmental monitoring' program 'and"the results thereof at least.once per 12 months. k. The OFFSITE DOSE CALCULATION MANOAL and implementing procedure's at + least once per 24 months;. -? HOPE CREEK 6-11 Amendment No. 21. a L e

(

1

c 'l ADMINISTRATIVE CONTROLS

1. -

The PROCESS CONTROL PROGRAM and implementing procedures for process-ing and packaging of radioactive wastes at least once per 24 months; and. The performance of activities required by the Quality Assurance Program m. ffluent and environmental monitoring at least once per 12 months. The above audits [teg4-1Jbe conducted by theWQuality Assurance Department' d or an independent consultant. Audit plans anc final audit reports shall.be l reviewed by the OSR tr ur : i::- aaK shfl-Yice hs;4sst and Ch.ief Nuc.leat-OMeer l ~ 6.5.2.4.4 Records of OSR a :tivities shall' be maintained. Reports of reviews and audits shall be prepare tand distributed as indicated below: 2 ) a. The results of re-tiews performed oursuant' to Section' 6.5.2.4.2 shall be reported-to the""i: "rs t r.; --.Jat.least monthly. j b. Audit ~ reports prepared pursuant to Specification 6.5.2.4.3 shall be i forwarded by the auditing organization to the Vice President and Chief Nuclear Officer and to the management positions responsible for the areas audited (1) within 30 days afteF completion of the audit for + those audits" conducted by*th C -- nr Xuality Assurance Department, ' conducted by an independent consultant.and (2) within 60 days aft etioT of the audit for those audits L FuMcTlg t 6.5.2.5 ONSITE SAFETY REVIEW GROUP (SRG) <4 6.5.2.5.1 The SRG shall function to provide: the review of plant design and operating experience for potential opportunities to improve plant safety; evalua-tion of plant operations and maintenance activities; and advice to management on the overall quality and safety of plant. operations. The SRG shall make recommendations for revised procedures, equipment modifica-i tions, or other means of improving plant safety to appropriate station / corporate management. RESPONSIBILITIES 6.5.2.5.2 The SRG shall be responsible for: Review of selected plant operating characteristics, NRC issuances, a.- industry advisories, and other appropriate sources of plant design. and operatifig experience information which may indicate areas for improving plant safety. b. Review of selected facility features, equipment, and systems. Review of selected procedures and plant' activities including main-c. tenance, modification, operational problems, and operational, analysis. t I HOPE CREEK 6-12. . Amendment.No. 21 ~

s 4

_ - ~ - -. _ i w !1 ADMINISTRATIVE CONTROLS d. Surveillance of selected plant operations and maintenance. activities to provide independent verification" that they are performed correctly-I and-that human errors are reduced to as low as reasonably achievable. AMM The Nucles Me.h Denufrv'ed-6.5.2.6 shall. report to and advis's the Vice President and Chief Nuclear _ i Officer on. osa areas of responsibility _specified in Sections 6.5.2.4 and 6.5.2.5. 6.5.3 TECHNICAL REVIEW AND CONTROL 1 ACTIVITIES l 6.5.3.1 All programs and procedures required by Technical Specification 6.8 and changes thereto, and any other proposed procedures or changes thereto, which affect plant nuclear safety as determined by the General Manager - Hope Creek Operations, other.than editorial'or typographical changes, shall be' reviewed as follows: PROCEDURE RELATED DOCUMENTS

6. 5. 3. 2 Prpcodures, Progr'ans and changes thereto shall be reviewed. as follows:-

Each newly created hrocedura, pro ram or' change thereto shall'be a. independently reviewed by an indi idual, knowledgeable'in the area affected other than the individua'l who prepared the procedure, pro-gram or procedure change, but'who may be from the same organization as the individual / group which prepared the procedure or procedure ~ change. Procedures other than Station ~ Administrative procedures l will be approved by the appropriate station Department Manager or by the General Manager

  • Hope Creek Operations..Each station Department

[ Manager sna11 be responsible for 'a pre-designated class of proceduresi 4 i The General Manager - Hope Creek Operations shall approve Station-Administrative Procedures, Security. Plan-implementing procedures and Emergency Plan implementing procedures. b. On-the-spot changes to procedures which clearly do not change the intent of the approved procedures shall be' approved by two members of the plant management staff, at_least one of whom holds a Senior 3 i Reactor Operator's License. Revisions to procedures which may l involve a change in~ intent of the approved procedures, shall be reviewed in'accordance with Section 6.5.3.2.a above, Individuals responsible for reviews' performed-in accordance'with item c. 6.5.3.2.a above shall be approved by the 50RC Chairman and designated asa Station Qualified Reviewer. A system of Station Qualified: Reviewers shall be maintained by the 50RC Chairman. Each review f 4 shall include a written determination oflwhether or. not' additional N Not responsible for sign-off function. HOPE CREEK 6-13 Amendment No. 21 1

) ' ADMINISTRATIVE CONTROLS ' quirt, CL cross-disciplinary review is necessary. If deemed necessary, such i IO CFf. Jo,gy review shall be performed by the appropriate designated review J g personnel. The Station Qualified Reviewers snall meet or exceed the g qualifications described in Section 4.4 of ANS 3.1, 1981, d. IfthepeartmentMana r determ es that the documents involved the documents shall be forwarded .ee OSR rev'ew an so or an independent review to deter-g mine whether or not an unrFviewed safety question is involved. Pur-suant to 10 CFR 50.59, NRC approval of items involving unreviewed-safety questions or requiring Technical Specification changes shall J be obtained prior to implementation. NON-PROCEDURE RELATED DOCUMENTS j i 1 6.5.3.3 Tests or experiments, and ch n equipment or systems shall be forwarded for 50RC review and also toj for an independent review to determine whether or not an unreviewed safety question is involved. The results of M reviews will be provided to 50RC. Recommendations for approval are made by 50RC to the General Manager - Hope Creek Operations. Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions or requiring Technical Specification changes shall be obtained prior to implementation. RECORDS AND REPoETS n 6.5.3.4 Written records of reviews performed in accordance with item 6.5.3.2a above, including recommendations for approval or disapproval, shall be maintained. ies shall be provided to the General Manager - Hope Creek Operations, 50RC, I, and ne WDr = nacassary when their reviews are required. ehs OS2 s+sSGI 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: The Commission shall be notified pursuant to the requirements of a. l Section 50.72 to 10 CFR Part 50 and a report submittal pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and 1.' b. Each REPORTABLE EVENT shall be reviewed e 50RC, and the results-of this review shall be submitted to the and the Vice President and Chief Nut: lear Officer. L gg

6. 7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

The NRC Operations Center shall be notified by telephone as soon as - a. possible and in all cases within 1 hour. Th Vice President and Chief-Nuclear Officer and the General Manager - shall be notified within 24 hours. Ovalh Assuranca, and b)uebe SE49 HOPE CREEK 6-14 Amendment No. 21

' i ADMINISTRATIVE CONTROLS I i b. A Safety Limit Violatierr Report shall be prepared. The report shal1 l be reviewed by the 50RC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violationr upon unit components, systems, or structures, and (3) corrective action taken to prevent r.eure.ne. The Safety Limit Violjf.glin AstoraN.A ed Nucle r Se(Al c. lon Report shall be submitted to the Commission, i the General' Manager C.;;;;r ;;fet. ";.u.f and. the Vice President and Chief Nuclear Officer within 30 days of the violation. d. Critical operation of the unit shall not be resumed until authorized by the Commission. 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented.:and maintained covering the activities. referenced below: The applicable procedures recommended in Appendix A of Regulatory. a. Guide 1.33, Revision 2, February 1978. b. .The applicable procedures required to implement the requirements;of NUREG-0737 and supplements' thereto.

  • c.

Refutiing operations., * ? d. Surveillance and test activities of sa'ety-related equipment'.- f e. Security Plan implementation. 7 ( f. Emergency Plan implementation. g. Fire Protection Program implementation. h. PROCESS CONTROL PROGRAM implementation, i 0FFSITE DOSE CALCULATION MANUAL implementatio'n. l j. Quality Assurance Program for effluent and environment monitoring. f 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall.be reviewed and approved in.accordance with specification 6.5.1.6 or 6.5.3, as appropriate, prior to implementation and reviewed periodically as set forth in administrative procedures. 6.8.3 On-the-Spot changes to procedures of Specification 6.8.1 may be made provided: The intent of the original procedure is not altered; a. b. The change is approved by two members of the unit management staff, at least one of whom holds a-Senior Reactor Operator' license on;the unit affected; and HOPE CREEK 6-15 Amendment No. 21-i F a ,}

1 l ADMINISTRATIVE CONTROLS PROCEDURES AND PROGAAMS (Continued) c. The change is documented and receives the same level of review and approval as the original procedure under Specification 6.5.3.2a v within 14 days of implementation. 6.8.4 The following programs shall be established, implemented, and maintained: a. Primary Coolant Sources outside Containment A program to reduce leakage from those portions of systems outside-l containment that could contain highly radioactive fluids during'a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, Containment Hydrogen Recom-- biner, Hs/03 analyzer, Post-Accident Sampling, Control Rod Drive Hydraulic'(Scram Discharge portion) systems; The program shall include t the following: t. l

1.. Preventive maintenance and periodic visual inspection requirements, and 2.

A service pressure leas test for e'ach system at, refuel'ing cycle intervals' or less. b In-PlantRadjtionMonitorina' ~ A program which will ensure the capability to accurately.detemine the airborne iodine concentratien in vital. areas under accident conditions. This program shall include the following: 1. Training of personne1~,. 2. Procedures for monitoring, and 3. Provisions for meintenance of sampling and analysis equipment. c. Post-accident Samolino A program which will ensure the capability to obtain and analyze reactor i l coolant, radioactive fodines and particulates in plant gaseous afflu-ents, and containment atmosphere samples under accident conditions. The program stia11 include the following: s 1. Training of personnel. 2. Procedures for sampling and analysis,-and l 3. Provisi6ns for maintenance of sampling and analysis equipment. l L HOPE CREEK 6-16 1 --._,.,-s,-._.... ._.m .. -. -.. -. ~. -, -.. -,,..

i l. l l ADMINISTRATIVE CONTROLS ^l 1 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS i 6.9.1~ In addition to the applicable reporting requirements of Title 10, Code of Federal Reculations, the following reports shall be submitted to thel-"-- ' LIS E.4 Administrator 2 :.u n :..= r r::: = = : = iunless otherwise noted. STARTUP REPOR 8 6.9.1.1 A' summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, i thermal, or hydraulic performance.of the unit. 6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory opera-tion shall also be described. Any additional specific details required in license conditions based on other conditments shall be included in this report. 6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commence-6 j ment of commercial power operation, or (3) 9 months following initial criticality, i whichever is earliest. If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed. n ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. ' The i ni tl ei, +. ; ehell ' - - "'" " " - ^ ^ I i..!;iel c.iticelity.I 6.9.1.5 Reports required on an annual basis.shall include: a. % tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions ** (e.g., reactor operations and surveillance, 1 ftA single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

  • A This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

HOPE CREEK 6-17

i

.Whc reading dmW J ADMINISTRATIVE CONTROLS l inservice inspection, routine maintenance, specia 1 maintenance j [ describe maintenance), waste processing, and re1 ueling). : The dose i assignments to various duty functions may be estLeated tasarl on pocket -1 dosimeter, thermoluminescent dosimeter (TLD), or, ggemeasure-ments. Small' exposures totalling less than 20% o t e nd'vidual 1 total dose need not be accounted for. In the aggregate, at least I 80% of the total whole-body dose received from external-sources should be assigned to specific major work functions; and 1 b. Documentation'of all challenges to main steamline safety / relief j valves. ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reporting covering the I operation of the unit during the previous calendar year shall be submitted. prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality; The annual radiological environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a com-parison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observe:1 impacts of the plant operation on the environment. The reports shall also include the risults of land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the l monitoring, the report shall provide an analysis of the problem and a planned a l course of action to alleviate the problem. l l The annual radiological environmental operating reports shall include summarize'd and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. Deviations i from the sampling program identified in Technical Specification 3.12.1 shall be reported. In the event that some results are not available for inclusion with l the reports, the report shall be submitted noting and explaining the reasons for the missing results. The missina data shall be suh=itted as annn an possible in a supolementary report.~ I at least +Wo lapWe. enaPS i ces. carrir$ swmph,n3 l- [ineens neac ea SITE BouNDAr.und a ser.e4 avark ee, mort. disht locabs, all I ihe reporu snai s also include the following: a summary descriot' on of the radiological environmental monitoring program;;; x M :11 M n; h = M ;= M I keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Comparison Program, as required by Specification 3.12.3. i f The report shall also include the results of specific activity analysis in which the primary coulant exceeded the limits of Specification 3.4.5. The l following information thall be included: (1) Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis HOPE CREEK 6-18 f 1 . ~.

1 l i q 1 1 l l '1 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) .i Clean-up system flow history. starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per. gram as a function of time 'i for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit. SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6. 9.1. 7 Routine radioactive release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The period of the first report shall begin with the date of initial criticality. t The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the-unit as. outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liqu'id-an'd Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1,* Jdne 1974, with data summarized on a quarterly bas'is following the format,of Appendix 8 thereof. The radioactive effluent release report to be submitted within 60 days after l January 1 of each year shall include an annual summary of hourly meteorological-i data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, and atmos-pheric stability, and precipitation (if measured) on. magnetic tape, or in the form of joint frequency etistributions of wind speed, wind direction, and atmos-- pheric stability. This same report shall include an assessment of the radia-- tion doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same' report shall also include.an assessment of the radiation doses from radioactive liquid and laseous effluents to MEleERS OF THE PUBLIC due to their activities inside the ' ITE BOUNDARY (Figure 5.1.1-1 during the report period. All ' assumptions used in making these assessmen)ts,-i.e., specific activity, exposure time and l location, shall be included in these reports. The historical annual average meteorology or the meteorological conditions concurrent with the time. of release of. radioactive materials in gaseous effluents (as determined by-sampling frequency and measurement) shal1:be-used for determining the gaseous pathway-doses. The assessment of radiation doses shall be performed in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM).- The Semiannual Radioactive Effluent Release Report shall identify those radiological environmental-sample-parameters and-locations where it is not possible or practicable to continue. to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway-and the new location (s) for obtaining replacement samples should be identified. The report should also include'a revised figure (s) and table (s) for the CDCM. reflecting the new location (s). HOPE CREEK 6-19 [ i l- - -.-n ~. - - -

i i ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Contil:ued) The radioactive effluent release report to be submitted within 60 days after { Januarv 1, of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cy'cle sources (including doses from primary effluent path-ways and direct radiation) for:the previous 12 consecutive months to show con-formance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribu-tion from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. -) The radioactive affluents release shall include the following information for i each class of solid waste (as defined by'10 CFR 61) shipped offsite during the report period: a. Container volume, l b. Total curie quantity (specify whether determined by measurement or estimate), Principal radionuclide (specify whether determined by measurement c. or estimate), d. Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms), l Type'of container (e.g., LSA, Type A, Type B, Large Quantity), and e. l f. Solidification agent (e.g., cement, urea formaldehyde). The radioactive effluent release reports shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis. The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP), OFFSITE DOSE CALCULATION MANUAL (00CM) or radio-active waste systems made during the reporting period. MONTHLY OPERATING REPORTS

6. 9.1. 8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Reguiator" Commission, Docu-ment Control i)esk. Washincton. D.C. 20555, with a copy to the ":::::

'lAdmin-1 istrator %f ta: "n i:::' Off = fno later than the 15th of each monthbrollowing the calendar monti covered by a raaart SPECIAL REPORTS . MM Ii. 4 6.9.2 Special reports shall be submitted to the U.S.. Nuclear Regulatory Commiss'on, Document tontrol Desk. Washinaton. DC 20EEE. with a copy to the ()5Nff T:7 zd Administratort:f th: "::i ::T Of'ic; cf :L.t:0lwithin the time perloa specified for each report. Q, gg,p on,, 6.9.3 Violations of the requirements of the fire protection program described in the Final Safety Analysis Report which would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be submittedtotheU.S.NuclearRegulatoryCommisg_n,DocumentControlDesk. Mashincton. DC 20555, with a copy to the T x Administrator f the " d cr:! [

^,77h ;f 9221via the Licensee Event Report Systesqwithin 30 dayL. T,3gg Q HOPE CREEK 6-20 -l n g ff,,l-Amendment M. n

i ADMINIS1RATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. SPECIAL REPORTS 6.10.2 The following records shall be retained for at least 5 years: a. Records and logs of unit operation covering time interval at each power level. b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety. c. All REPORTABLE EVENTS submitted to the Commission. d. Recoro of surveillance activities, inspections, and calibrations required by these Technical Specifications. P Records of changes made to the procedures required by Specification e. 6.8.1. f. Records of radioactive shipments. g. Records of sealed source and fission detector leak tests and results. 1 h. Records of annual physical inventory of all sealed source material of record. 6.10.3 The following records shall be retained for the duration of the unit Operating License: Records and drawing changes reflecting unit' design modifications made a. to systems and equipment described in the Final Safety Analysis' Report. b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories, hecords of radiation exposure for all individuals entering radiation c. control areas. 4 d. Records of gaseous and liquid radicactive material released-to the

environs, Records of transient or operational cycles for those unit components e.

identified in Table 5.7.1-1. HOPE CREEK 6-21 l

1 L I i ALMINISTRATIVE CONTROLS = RECORD RETENTION (Continued) f. Records of reactor tests and experiments. g. Records of training and qualification for current members of the unit _

staff, i

h. Records of inservice ir.spections performed pursucnt to these Technical Specifications. 1 1 1. Records of quality assurance activities required by the Quality-1 Assurance Program, j. Records of reviews performed for changes made to procedures or equip-j ment or reviews of. tests and experiments pursuant to'10 CFR 50.59.

i Sc EC 1

k. Recorcs offmeetings &nd h Z Z activities. ) 2----- c5f4,1 J 1. Records of the snubber service life monitor ng pursuant to Technical $pecification 4.7.5. m. Records of analyses required by the radiological environmental monitoring program which would permit evaluation of the: accuracy of the analyses at a later date.- This should include procedures effective at specified times and QA records showing that these _ procedures were followed. j 6.11 RADIATION PROTECTION PROGRAM. 6.11.1 Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, main-tained, and adherec' to for all operations inv)1vina personnel radiation l exposure. J4 -the @ rWieHm arsa. Is astaVished. 4r o. ytried of 30 days er itss,. f diced surveillancoio Pre.vad WauthorittJ s% rway be usaJ (os+aaJ ef % 9 6.12 HIGF RADIATION AREA e6cetSS Cordrolt dtsccNJ obout, par-to cf;It,20.%o5 f (c)(2) GC(.4), I 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph-20.203(c)(2) of.10 CFR Part 20, each high radiation area-in which the intensity 5 of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr* shall be i barricaded and conspicuously posted as a high radiation area and entrance thereto i shall be controlled by requiring issuance of a Radiation Work Permit (RWP)**. 7 Any indiviciual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

  • Measurement made at 18 inches from source of radioactivity.
    • Radiation protection personnel or personnel escorted by' radiation protection personnel shall be exempt from the RWP issuance requirement during the per-formance of their assigned radiation protection duties, provided they are-

'otherwise following plant radiation protection procedures'for_ entry into high radiation areas. 1

HOPE CREEK 6-22 f

ADMINISTRATIVE CONTROLS a. A radiation monitoring device which continuously indicates the radia-tion dose rate in the area. b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated - dose is received. Entry into such areas with this monitoring device [. may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them. c. A radiation protection qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate I monitoring device who is responsible _for providing. positive control = over the activities within:the area and shall perform periodic radiation surveillance at the frequency specified by!'h: M i:tical. . I P :t:cti= Meni;;rS the RWP. 6.12.2 In addition to the requirements of Specification 6.12.1, areas access-ible to personnel with radiation levels,such that a major portion of the body could receive-in 1 hour a dose greater than 1000 mrem

  • shall be provided with locked. doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Senior Nuclear Shift Supervisor on duty and/or the radiation protection supervision.

Doors shall remain-locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that arec For individual areas accessible to personnel with radiation levels such that-a s.ajor portion of the body could receive in 1 hour l a dose in excess of 1000 mrem

  • that are located within large' areas, such as the containment, where no enclosure exists for purposes of locking,. and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light-shall be activated as a' warning device.

In lieu of the stay time specification of the RWP, continuous surveillance direct or remote _(such as use of closed circuit TV cameras), may be made by per-sonnel qualified in radiation protection procedures to'previde positive exposure control over the activities within the area. 6.13 PROCESS CONTROL PROGRAM-(PCP)- 6.13.1 The PCP shall be approved by the Commission prior to implementation. 6.13.2 Licensee initiated, changes to the PCP: 1. Shall'be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was ; sade,- This submittal shall contain: a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;

  • Measurement made'at 18_ inches from source of radioactivity.

t HOPE CREEK 6-23 --r ~,- c.-,_. -.

l e l l ADMINISTRATIVE CONTROLS I PROCESS CONTROL PROGRAM (PCP) (Continued) a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b. A determinatiun that the change did not reduce the overall j conformance of the solidified waste product to existing criteria for solid wastes; and c. Documentation of the fact that'the change has been reviewed and found acceptable by the 50RC. 2. Shall become effective upon review and acceptance by the 50RC. 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation. 6.14.2 Licensee initiated changes to the ODCM: 1. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain: a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s); b. A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and c. Documentation of the fact that the change has been reviewed and found acceptable by the SORC. 2. Shall become effective upon review and acceptance by the SORC. 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSlTMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid): gg 1. Shall be reported to the Commission in the for the period in which the evaluation was reviewed by SORC. The discussion of each chang shall contain: K0PE CREEK 6-24

t G5 ADMINISTRATIVE CONTROLS MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT hYSTEMS (Continued) a. A summary of the evaluation that led to the determination that thechangecouldbemadeinaccordancewith10CFRiEifi[50.59; 7 b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; d. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; e. An evaluation of the change, which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto; f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made; g. An estimate of the exposure to plant operating personnel as a result of the change; and h. Documentation of the fact that the change was' reviewed and found acceptable by the SORC. 2. Shall become effective upon review and acceptance by the 50RC. r t HOPE CREEK 6-25 ,}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20006B533&oldid=4664260"