ML20196E654

Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively

ML20196E654
Person / Time
Site:	Hope Creek
Issue date:	06/21/1999
From:	Public Service Enterprise Group
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ML20196E652	List: ML20196E647 ML20196E654
References
NUDOCS 9906280363
Download: ML20196E654 (11)

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l ATTACHMENT 1 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISED TECHNICAL SPECIFICATION PAGES FOR LCR H99-02 i

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9906280363 990621 'T PDR ADOCK 05000354.3 P

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HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISION 3 TO THE TECHNICAL SPECIFICATIONS (TS)

TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES

. The following Technical Specificat3ns for Facility Operating License No. NPF-57 are affected by this change request:

Technical Specification Page INDEX ii, ix, xv, xvi, xviii, xxi, xxii, and xxiv DEFINITIONS 1-4,1-6 and 1-8 3/4 3.7.10 3 / 4 3-91 thru 3-95 3 /4 3.7.11 3 / 4 3-96 thru 3-102 3 /4 11.1.1 3 / 4 11-1 thru 11-4 3 /4 11.1.2 3/4 11-5 3 /4 11.1.3 3/4 11-6 3 /4 11.2.1 3 / 4 11-8 thru 11-11 3/4 11.2.2 3/4 11-12 3/4 11.2.3 3/4 11-13 3 /4 11.2.4 3/4 11-14 3 /4 11.2.5 3/4 11-15 3 /4 11.2.8 3/4 11-18 3 /4 11.3 3/4 11-19 3/4 11.4 3/4 11-20 3 /4 12.1 3 / 4 12-1 thru 12-12 3 /4 12.2 3/4 12-13 3/4 12.3 3/4 12-14 6.8.4 6-16b l

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Il@.EK ADMINISTRATIVE CONTROLS maamammmmmmmmmmmmmmensemommmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmme SECTION PAfeg 6.1 RESPONSIBILITY...........................................

61 6.2 ORGANIZATION............

6-1 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS.....................

6-1 6.2.2 UNIT STAFF............

6-1 Figure 6.2.1-1 (Deleted)................

6-3 Jk/'

Figure 6.2.2-1 (Deleted)........................

6-4 Table 6.2.2-1 Minimum Shif t Crew Composition Single Unit Facility.............

6-5 6.2.3 SHIFT TECHNICAL ADVISOR..............................

6-6 6.3 UNIT STAFF OUALIFICATIONS.................................

6-6 6.4 TRAINING..................................................

6-6 6.5 REVIEW AND AUDIT (THIS SECTION DELETED)..................

6-6 6.6 REPORTABLE EVENT ACTION............

6-14 6.7 SAFETY LIMIT VIOLATION...

6-14 6.8 PROCEDURES AND PROGRAMS.............................

6-15 6.9 REPORTING REOUIREMENTS...................................

6-17 I

6.9.1 ROUTINE REPORTS............

6 - 1*/

STARTUP REPORT......

6-17 ANNUAL REPORTS.......

6-17 ANNUAL RADIOLOGICAL ENVIRONMENTAL CPERATING REPORT.,

6-18 g

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RADIOACTIVE EFFLUENT RELEASE REPORT..................

6-19 MONTHLY OPERATING REPORTS.

6 20 CORE OPERATING LIMITS REPORT.....

6-20 6.9.2 SPE;IAL REPORTS......

6-21 HOPE CREEK' xxiv Amendment No.

r LCR H99-02 INSERT A 1.27 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiologica!

l Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 l

and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Specifications 6.9.1.6 and 6.9.1.7.

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lNSERT B 1.33 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packing of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

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j ADMZNISTRATIVE CONTROLS l

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PROCEDURES AND PROGRAMS (Continued) 6.8.4.g.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall br implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

2) Limitations on the concentra: ion of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR / art 20, Appendix B, Table II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in th'.

JDCM,

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendLr quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, HOPE CREEK 6-16c Amendment No.

L ADMINISTRATIVE CONTROLS y.

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PROCEDURES AND PROGRAMS (Continued) i 6.8.4.g.

Radioactive Effluent Controls Program 4

8)' Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas.beyond the SITE BOUNDARY conforming to Appendix I to 10 i

CFR Part 50, I

9). Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on venting and purging of the containment through the Reactor Building Ventilation System, Hardened Torus Vent, or the FRVS to maintain releases as low as reasonably achievable, and i

11) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources confor

'g to 40 CFR Part 190.

h.

Radiological Environmental Monitoring Program i

A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall I

provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluents monitoring program and modeling of the j

environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance oV Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the i

methodology and parameters in the ODCM, 1

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of j

the measurements of radioactive materials in environmental i

sample matrices are performed as part of the quality assurance program for environmental monitoring.

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6-16d Amendment No.

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1.CR H99-02 INSERT O 6.9.1.6 The Annual Radiological Environmental Operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shallinclude summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outiined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix l to10 CFR Part 50.

INSERT E 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previot.s calendar year shall be submitted by May 1 of each year. The report shallinclude a summary of the quantitics of radioactive liquid and gaseous effluents and solid wastes released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix l to 10 CFR Part 50.

ADMINISTRATIVE CONTROLS

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(Cont ved)

-r afte he radiot activity a redu to limit. I h result e

14 imelude to and time sampli and tr toiodine e centrations;

) Clean-up yeten flow h tory et ing 4 e prior to first sample

/othere in which limit was eeded; Gr f he I-131 co entration and o ioiodine i co ra t

crocuries gram as a fune on i

of t for the dur ion of t e

Lf L etivity the steady-stat 1

13 and (5) T time dur ion i

specific a ivity of the pr ry laat eac the rad odine lig a

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6.9.1.dRadios release rte cover the operation the unit shall 7

g be submitted May 1 of ch year and accordance with requiremente 10cFRSO.36a The r etive of uent rolea.. s et shall inclu a summary cf th quan ties of r osctive liquid gaseous effl to and solid va e re ased from unit as outi in Pagulato Guide 1.21, " Mea ring,

aluating, Reporting osctivi y in So d Wastes and Re1 see of Radioacti Materiale in L id and seous ifluents from Li t-Water-cool Nuclear r F1sato,*

ision 1,j 1

4, with data e imod on a quart ly basis follow g the fochts of pipend a 3 thereo T

radioactive of uent ce re et shall include annual suana of ourly meteorol cal dat y

over the previ e year. This ual summary may be ither i fo of an hour-by-r listing of w d speed, wind directi, and a er stability, and ipitation (i measured) magnetic t

, or in t to of joint i distribution of wind e wind dir Lon, and atmos eric stability.

report shall nelude an asses at of the radia on doses due to radioactive gutd and g eous affl ate released fr the unit or sta on during the evious cal dar year.

Th report shall al include an asse at of the r ation dose from dioactive liqui and gaseous eff1 to to MEMBERS TER PUBLZ due to the activities inet the SITE SOUND (Figure 5.1.1-during t report port All assumpti used La making es assosomente i.e.,

spec ic activity exposure t and location, e 11 he included these r

s. The his etcal mamuai a ege esteorology the meteorolog 41 conditi e concurren with the t of release of r osctive materia in gaseou effluente (

dote by sempting acy and sea t) e 1 he used to Lag the g pathway doses.

asses t of radiati doses shal performed is ne vtth the Its noss

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s Radiesetive 3 lueet Release et shall tify these adiological environmental e le parameters locat it is possible practicable t oestimme to obt samples the media of boice at t most desired 1 Les er time. ta ition, t cesse of the vailabili of eamples f the pathwey he esw toe les(e) for alaing rep 1 emont samples bould he identif

. The should al Laclude a r Lead figur e) and table (e) e the 0001. flecting t locatto e).

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't.CR H99-02 INSERT G 6.13 PROCESS CONTROL PROGRAM (PCP)

' Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.n. This documentation shall contain:

(1).

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and (2)

A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the SORC and the approval of the Plant General Manager.

INSERT H 6.14 OFFSITE DOSE CALCULATIONAL MANUAL (ODCM)

Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.n. This documentation shall contain:

1) Sufficient information to' support the change together with the appropriate analyses or evaluations justifying the changes (s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by the SORC and the approval of the Plant General Manager.

' c.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

ATTACHMENT 2 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISED TECHNICAL SPECIFICATION PAGE FOR LCR H99-05 Index Page vi l

NDEA L:MIT!NG CONDITIONS FOR OPERATION AND SURVEILLAN 3E:':0N DAGE 3.42.2 APRM SETPOINTS.

3/4 2-2 3, 4. 2. 3 4:N:.%M CRITICAL DOWER RATIO...

3/4 2-3 I

3/4.2.4 1.'NEAR HEAT GENERATION RATE......

I 3/4 2-5 3/4.3 !NOTRL' MENTATION l

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.......

3/4 3-1 Table 3.3.1-1 Reactor Protection System Instrumentation..........................

3/4 3-2 7.oi. 3.3.12ye;3;.-?re;;;;i:nOj;;::";;;;n;;

h aa, a a Figure 4.3.1.1-1 Reactor Protection Systen Surveillance Requirements...........................

3/4 3-7 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION......................

3/4 3-9 Table 3.3.2-1 Isol nfon Actuation Instrumentation.......

3/4 3-11 Table 3.3.2- [ ola' tion Actuation Instrumentation Setpoints..............................

3/4 3-22 Lu i, 3.1.-2-3

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J/* J - (. 7 Table 4.3.2.1-1 Isolation Actuation Instrumentation

' Surveillance Requirements.................

3/4 3-28 1

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HOPE CREEX vi.

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