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4 NPF-38-216 ATTACHMENT A EXISTING SPECIFICATION I
e 4
9907270130 990715 PDR   ADOCK 05000382 l       P               PDR
NPF-38-216 ATTACHMENT A EXISTING SPECIFICATION I
9907270130 990715 PDR ADOCK 05000382 l
P PDR


      . o. -
. o. -
111D11 ADMINISTRATIVE CONTROLS SECTION                                                             f, gig 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-22 6.12 HIGH RADIATION AREA........................................ 6-22 6.13 PROCESS CONTROL PR0 GRAM.................................... 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................ 6-24 1
111D11 ADMINISTRATIVE CONTROLS SECTION f, gig 6.11 RADIATION PROTECTION PR0 GRAM...............................
6.15 CONTAINMENT LEAKAGE RATE TESTING PR0 GRAM................... 6-24       l i
6-22 6.12 HIGH RADIATION AREA........................................
WATERFORD UNIT 3                   XVIII                   Amendment No. 68,124
6-22 6.13 PROCESS CONTROL PR0 GRAM....................................
6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................
6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PR0 GRAM...................
6-24 l
i WATERFORD UNIT 3 XVIII Amendment No. 68,124


l,q. de l             ADMINISTRATIVE CONTROLS l             HIGH RADIATION AREA (Continued)
l,q.
: 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 level in the area has been established and personnel have been made knowledgeable of them.
de l
: c. A health physics qualified individual (i.e., qualified in radiation protection procedures) l                         with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
ADMINISTRATIVE CONTROLS l
6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mroms* but less than 500 rads" shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall             I 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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000 mrams* but less than 500 rads" that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably                   l constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance         ;
HIGH RADIATION AREA (Continued) b.
may be made by personnel qualified in radiation protection procedures to provide positive               j exposure control over the activities within the area.
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 level in the area has been established and personnel have been made knowledgeable of them.
c.
A health physics qualified individual (i.e., qualified in radiation protection procedures) l with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mroms* but less than 500 rads" shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall I
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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000 mrams* but less than 500 rads" that are located within large areas, such as PWR 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 waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive j
exposure control over the activities within the area.
613 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
613 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:
6.13.2 Licensee-initiated changes to the PCP:
: a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:
a.
: 1.     Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
                " Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
" Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
WATERFORD - UNIT 3                               6-23                     AMENDMENT NO. 66:446,146
WATERFORD - UNIT 3 6-23 AMENDMENT NO. 66:446,146


.; d
d ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 2.
      . ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other i
: 2.     A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other i
applicable regulations.
applicable regulations.
: b. Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.                                               I 4
b.
614 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1       The ODCM shall be approved by the Commission prior to implementation.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.
6.14.2       Licensee-initiated changes to the ODCM:
I 4
: a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document shall contain:
614 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
: 1.       Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
6.14.2 Licensee-initiated changes to the ODCM:
: 2.     A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
Shall be documented and records of reviews performed shall be retained as required a.
: b. Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.                                                 I
by Specification 6.10.3p. This document shall contain:
: c. Sha!! be submitted to the Commission in the form of a complete, legible copy of the
1.
        ,            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.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2.
A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l 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 PORC and the approval of the General Manager Plant Operations.
I c.
Sha!! 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.
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.
615 CONTAINMENT I FAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
615 CONTAINMENT I FAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated containment intamal pressure for the design basis loss of coolant accident, P,, is 44 psig.
The peak calculated containment intamal pressure for the design basis loss of coolant accident, P,, is 44 psig.
The maximum allowable containment leakage rate, L., is 0.5% of containment air weight per day atP,.
The maximum allowable containment leakage rate, L., is 0.5% of containment air weight per day atP,.
WATERFORD - UNIT 3                                 6-24           AMENDMENT NO. 00,04,110,124,146
WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,146


  .' e./
e./
CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued) e ._p._ .e. ._
CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued) e._p._.e.._
: a. Overall containment leakage rate acceptance cri:eria is 51.0 L,. During the first unit startup following each test performed in accordance with this program, the overall containment leakage rate a"e:eptance criteria are 5 0.60 L, for the Type B and Type     {
a.
C tests and s 0.75 L, for Type A tests.
Overall containment leakage rate acceptance cri:eria is 51.0 L,. During the first unit startup following each test performed in accordance with this program, the overall
: b. Airlock acceptance criteria are:
{
: 1. Overall air lock leakage rate is s 0.05 L, when tested at 1 P,.
containment leakage rate a"e:eptance criteria are 5 0.60 L, for the Type B and Type C tests and s 0.75 L, for Type A tests.
: 2. Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig. I
b.
: c. Secondary containment bypass leakage rate acceptance critens is s 0.06 L, when         I tested at 1 P..
Airlock acceptance criteria are:
: d. Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when tested at 1 P,.                                                                         ,
1.
Overall air lock leakage rate is s 0.05 L, when tested at 1 P,.
2.
Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig.
I c.
Secondary containment bypass leakage rate acceptance critens is s 0.06 L, when I
tested at 1 P..
d.
Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when tested at 1 P,.
The provisions of Specification 4.0.2 do not apply to the test frequences specifed in the Containment Leskage Rate Testing Program.
The provisions of Specification 4.0.2 do not apply to the test frequences specifed in the Containment Leskage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
WATERFORD - UNIT 3                             6-25                       AMENDMENT NO. 494, 138
WATERFORD - UNIT 3 6-25 AMENDMENT NO. 494, 138


l I
l I
l l
l l
l 1
l 1
I l
1 I
NPF-38-216 ATTACHMENT B PROPOSED MARKED-UP SPECIFICATION
NPF-38-216 ATTACHMENT B PROPOSED MARKED-UP SPECIFICATION


                ,                            18Df2 ADMINISTRATIVE CONTROLS SECTION                                                             pgg 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-22 6.12 HIGH RADIATION AREA........................................ 6-22 5 11_ PROCESS CONTROL PR0 GRAM.................................... 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................ 6-24 6.15 CONTAIMENT LEAKAGE RATE TESTING PR0 GRAM................... 6-24     l 1
18Df2 ADMINISTRATIVE CONTROLS SECTION pgg 6.11 RADIATION PROTECTION PR0 GRAM...............................
POr                             ~         -
6-22 6.12 HIGH RADIATION AREA........................................
l C, %     (REM /3tlah I=dA Co N f!604ATio d (Jirk MAHA GEAA t"eJY fizo&zissA ..,G-b a , n vecwcn c sMcin cArwar Msc.T co <17acc /k'o6um ,, , c 2.C                     ,I
6-22 5 11_ PROCESS CONTROL PR0 GRAM....................................
                                                                                    #u 7-                    A
6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................
                                .A l
6-24 6.15 CONTAIMENT LEAKAGE RATE TESTING PR0 GRAM...................
l l
6-24 l
WATERFORD UNIT 3                     XVIII                   Amendment No. 68,124
POr
~
C, %
(REM /3tlah I=dA Co N f!604ATio d (Jirk MAHA GEAA t"eJY fizo&zissA..,G-b a, n vecwcn c sMcin cArwar Msc.T co <17acc /k'o6um,,, c 2.C
,I A
#u
.A 7-WATERFORD UNIT 3 XVIII Amendment No. 68,124


.+ l ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)
.+ l ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) b.
: 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 level in the area has been established and personnel have been made knowledgeabie of them.
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 level in the area has been established and personnel have been made knowledgeabie of them.
: c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the actnnties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
c.
l 6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel             )
A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the actnnties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
with radiation levels such that a major portion of the body could receive in one hour a dose               1 greater than 1000 mroms* but less than 500 rads ** shall be provided with locked doors to prevent unauthonzed entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision /designes. Doors shall               l 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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000             .
6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose 1
mroms' but less than 500 rads ** that are located within large areas, such as PWR 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 waming device, in lieu of the stay time specification         1 of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance             i may be made by personnel qualified in radiation protcction procedures to provide positive exposure control over the activities within the area.
greater than 1000 mroms* but less than 500 rads ** shall be provided with locked doors to prevent unauthonzed entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision /designes. Doors shall l
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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000 mroms' but less than 500 rads ** that are located within large areas, such as PWR 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 waming device, in lieu of the stay time specification 1
of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protcction procedures to provide positive exposure control over the activities within the area.
813 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
813 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:
6.13.2 Licensee-initiated changes to the PCP:
: a. Shall be documented and records of reviews performed shall be retained as required by ";n?.rt U n5 This documentation shall contain:
a.
: 1.     Sufficient information to support the change together with the appropnate analyses or evaluation justifying the change (s) and
Shall be documented and records of reviews performed shall be retained as required by ";n?.rt U n5 This documentation shall contain:
1.
Sufficient information to support the change together with the appropnate analyses or evaluation justifying the change (s) and
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
        ** Measurement made at 1 meter from the radiation source or from any surface that the radiation penetraW                         Ww Le- QualQ           Assu     - n e e iP<c nm                     n,wd
** Measurement made at 1 meter from the radiation source or from any surface that the radiation penetraW Ww n,wd Le-QualQ Assu - n e e iP<c nm
                              ~           -                                                     T NO. 66;446.146 AMENDM WATERFORD - UNIT 3                                  3
~
WATERFORD - UNIT 3 3
AMENDM T NO. 66;446.146


.l   ' .?
.l
'.?
ADMINISTRATIVE CONTROLE l
ADMINISTRATIVE CONTROLE l
PROCESS CONTROL PROGRAM (Continued)
PROCESS CONTROL PROGRAM (Continued) 2.
: 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.
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 PORC and the approval of the General Manager Plant Operations.                                                 I l l
b.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1     The ODCM shall be approved by the Commission prior to implementation.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.
6.14.2     Licensee-initiated changes to the ODCM:
I l
1
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
: a. Shall be documented and records of reviews performed shall be retained as required by Cf,m2,6v 0.10.0f,. This document shall contain:                                         ;
6.14.2 Licensee-initiated changes to the ODCM:
i
Shall be documented and records of reviews performed shall be retained as required a.
: 1.       Sufficient information to support the change together with the appropriate         !
by Cf,m2,6v 0.10.0f,. This document shall contain:
  +ke. O M df                     analyses or evaluations juctifying the change (s) and Assevm nCG
i 1.
                '"'"l     2.       A determination that the change will maintain the level of radioactive effluent bc72                             control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the             !
Sufficient information to support the change together with the appropriate
accuracy or reliability of effluent, dose or setpoint calculations.               '
+ke. O M df analyses or evaluations juctifying the change (s) and Assevm nCG'"'"l 2.
i
A determination that the change will maintain the level of radioactive effluent bc72 control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l 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 PORC and the approval of the General Manager Plant Operations.                                                 l
i b.
: c. Shall be submitted to the Commission in the form of a complete, legible copy of the
Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.
              ,            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.               ,
l c.
Each change shall be identified by markings in the margin of the affected pages,           !
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.
clearly indicating the area of the page that was changed, and shallindicate the date (e.g., month / year) the change was implemented.
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 shallindicate the date (e.g., month / year) the change was implemented.
815 CONTAINMENT I FAKAAF RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
815 CONTAINMENT I FAKAAF RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The peak calculated containment intamal pressure for the design basis loss of coolant accident, P , is 44 psig.
The peak calculated containment intamal pressure for the design basis loss of coolant accident, P, is 44 psig.
The maximum allowable containment leakage rate, L , is 0.5% of containment air weight per day atP,.
The maximum allowable containment leakage rate, L, is 0.5% of containment air weight per day atP,.
WATERFORD - UNIT 3                                 6-24           AMENDMENT NO. 00,04,110,124,146
WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,146


l . <.. .
l. <..
l                 .
l l
l
.T.ESI.itEi.f.8QrBAM (Continued) 1 Laakage rate w$s criteria are:
                                                          .T.ESI.itEi.f.8QrBAM (Continued) 1 Laakage rate w$s criteria are:
a.
: a. Overall containment lerakege rate acceptance criteria is a 1.0 L,. During the first unit   ;
Overall containment lerakege rate acceptance criteria is a 1.0 L,. During the first unit startup followmg each test perfomwd in accordance with this program, the overall I
startup followmg each test perfomwd in accordance with this program, the overall             I containment leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tosts and 3 0.75 L,for Type A tests.
containment leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tosts and 3 0.75 L,for Type A tests.
: b. Airlock acceptance criteria are:
b.
: 1. Overall air lock leakage rate is 5 0.05 L, when tested at 1 P,.
Airlock acceptance criteria are:
: 2. Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig.       l l                         c. Secondary containment bypass leakage rate acceptance criteria is 50.06 L, when           I tested at I P,.
1.
: d. Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when l                                 tested at1 P .
Overall air lock leakage rate is 5 0.05 L, when tested at 1 P,.
2.
Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig.
l l
c.
Secondary containment bypass leakage rate acceptance criteria is 50.06 L, when I
tested at I P,.
d.
Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when l
tested at1 P.
l The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
l The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisi,ons of Speedication 4.0.3 are applicable to the Containment Leakage Rate Testing             ,
The provisi,ons of Speedication 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
Program.
b
b
_L M S E /2 I ~                 L l
_L M S E /2 I ~
L l
l l
l l
L M S E FCT                                                       oa       n e v,-           PAGe (G- u                                 ;
L M S E FCT oa n e v,- PAGe (G-u x
x                                 >
l WATERFORD-UNIT 3 6 25 AMENDMENT NO. 494, 138 1
l WATERFORD- UNIT 3                                 6 25                     AMENDMENT NO. 494, 138 1
1
1


    .' o.
o.
INSERT 1 6.16     ( RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM )
INSERT 1 6.16
( RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM )
INSERT 2 ON NEXT PAGE (6-26) 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.
INSERT 2 ON NEXT PAGE (6-26) 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.
: a.       Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.
a.
: b.       Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.
: 1. A change in the Technical Specifications incorporated in the license; or
b.
: 2. A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
: c.       The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
1.
: d.       Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question as defined in 10CFR 50.59 shall be reviewed and approved by the NRC prior to implementation.
A change in the Technical Specifications incorporated in the license; or 2.
A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
d.
Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question as defined in 10CFR 50.59 shall be reviewed and approved by the NRC prior to implementation.
Implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
Implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
l l
l l
Line 167: Line 215:


,g.
,g.
                .                                                                                                    l l
INDEX j
INDEX                                                             j ADMINISTRATIVE CONTROLS l
ADMINISTRATIVE CONTROLS l
SECTIQN                                                                                               PAGE   ]
SECTIQN PAGE
1 6.11 RADIATION PROTECTION PROGM . .... .. .. . .. .                             . . . . . . . . . . 6-22 1
]
6.12 HIGH RADIATION AREA.. . ... . . . . . ....
1 6.11 RADIATION PROTECTION PROGM.............
                                                            . . . . . . . . . . . .        .... . . . .      6-22 6.13 PROCESS CONTROL PROGRAM.. .. ..               . . . . . . . . . . . . . . . . . . . . . . . . . 6-23 6.14 OFFSITE DOSE CALCULATION MANUAL.. . ..                               . . . . . . . . . . . . . 6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM... . .. .. ...,                                         6-24 6.16. (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM)... . . . . . .. ... . . .    . . . . . . . . . . . . . .                    . . . 6-25 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM.... . .                                           6-26 l
6-22 1
l 1
6.12 HIGH RADIATION AREA...............
l l
6-22 6.13 PROCESS CONTROL PROGRAM......
l WATERFORD - UNIT 3                         XVill                                     AMENDMENT NO. 60,124,
6-23 6.14 OFFSITE DOSE CALCULATION MANUAL.....
6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM...........,
6-24 6.16. (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM)...
6-25 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM......
6-26 1
l WATERFORD - UNIT 3 XVill AMENDMENT NO. 60,124,


l
l
,y .= /
, y
        . ADMINISTRATIVE CONTROLS I
.= /
HIGH RADIATION AREA (Continued)
. ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)
: 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 dor,e rate level in the area has been established and personnel have been made knowledgeable of         3 them.
I b.
: c. A health physics qualified individual (i.e., qualified in radiation protection       I procedures) with a radiation dose rate monitoring device who is responsible for     )
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 dor,e rate level in the area has been established and personnel have been made knowledgeable of 3
them.
c.
A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate 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 the facility Radiation Protection Superintendent-Nuclear in the RWP.
providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems* but less than 500 rads ** shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall remain locked except during periods of access by personnel under ar approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000 mrems* but less than 500 rads ** that are located within large areas, such as PW'R 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 waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillacD may be made by personnel qualified in radiation protection procedures to provide positi"a exposuro control over the activities within the area.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems* but less than 500 rads ** shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall remain locked except during periods of access by personnel under ar approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour a dose in excess of 1000 mrems* but less than 500 rads ** that are located within large areas, such as PW'R 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 waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillacD may be made by personnel qualified in radiation protection procedures to provide positi"a exposuro 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 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:
6.13.2 Licensee-initiated changes to the PCP:
: a. Shall be documented and records of reviews performed shall be retained by the Quality Assurance Program Manual. This documentation shall contain:
a.
Shall be documented and records of reviews performed shall be retained by the Quality Assurance Program Manual. This documentation shall contain:
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
* Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
          ** Measurement made at 1 meter from the radiation source or from any surface that the radiation     ;
** Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.
penetrates.                                                                                         l WATERFORD - UNIT 3                               6-23               AMENDMENT NO. 00,110,146; l
WATERFORD - UNIT 3 6-23 AMENDMENT NO. 00,110,146; l


, , , , , "=.4
,,,,, "=.4 ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 1.
                . ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)
Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and 2.
: 1.     Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and
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.
: 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.
: b. Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.                                     '
Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.                         ,
6.14 OFFSITE 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:
6.14.2 Licensee-initiated changes to the ODCM:
: a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:
a.
: 1.     Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:
: 2.     A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations. ,
1.
: b. Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations,
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2.
: 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.
A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
6.15 CONTAINMENT LEAKAGE RATE TESTING PROGrgyl                 _
b.
A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager Plant Operations, c.
WATERFORD - UNIT 3                               6-24     AMENDMENT NO. 00,04,110,124,140,
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.
6.15 CONTAINMENT LEAKAGE RATE TESTING PROGrgyl A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,140,


,,,: ..l 1
..l 1
        . ADMINISTRATIVE CONTROLS CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)
. ADMINISTRATIVE CONTROLS CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)
The peak calculated containment intemal pressure for the design basis loss of coolant accident, P., is 44 psig.
The peak calculated containment intemal pressure for the design basis loss of coolant accident, P., is 44 psig.
The maximum allowable containment leakage rate, L,. is 0.5% of containment air weight per day atP,.
The maximum allowable containment leakage rate, L,. is 0.5% of containment air weight per day atP,.
Leakage rate acceptance criteria are:
Leakage rate acceptance criteria are:
a
a a.
: a. Overall containment leakage rate acceptance criteria is s 1.0 L,. During the first unit startup following each test performed in accordance with this program, the overall containment leakage rate acceptance criteria ares 0.60 L, for the Type B and Type C tests and s 0.75 L for Type A tests.
Overall containment leakage rate acceptance criteria is s 1.0 L,. During the first unit startup following each test performed in accordance with this program, the overall containment leakage rate acceptance criteria ares 0.60 L, for the Type B and Type C tests and s 0.75 L for Type A tests.
: b. Air lock acceptance criteria are:
b.
: 1.     Overall air lock leakage rate is s 0.05 L when tested at 2 P,.
Air lock acceptance criteria are:
: 2.     Leakage rate for each door seal is s 0.005 L, when pressurized to210 psig.
1.
: c. Secondary containment bypass leakage rate acceptance criteria is s 0.06 L, when tested at 2 P,.
Overall air lock leakage rate is s 0.05 L when tested at 2 P,.
: d. Containment purge valves with resilient seals acceptance criteria is s 0.06 L, when tested ata P,.
2.
Leakage rate for each door seal is s 0.005 L, when pressurized to210 psig.
c.
Secondary containment bypass leakage rate acceptance criteria is s 0.06 L, when tested at 2 P,.
d.
Containment purge valves with resilient seals acceptance criteria is s 0.06 L, when tested ata P,.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
6.16 (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM)                                         l 1
6.16 (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM) l WATERFORD - UNIT 3 6-25 AMENDMENT NO. +24+38
WATERFORD - UNIT 3                               6-25                 AMENDMENT NO. +24+38


s ADMINISTRATIVE CONTROLS 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.
s ADMINISTRATIVE CONTROLS 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.
: a. Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.
a.
: b. Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.
: 1.     A change in the Technical Specifications incorporated in the license; or
b.
: 2.     A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
: c.     The Bases Control Program shall contain provisions to ensure that the %ses are maintained consistent with the UFSAR.
1.
: d.     Proposed changes to the Technical Specifications incorporated i's the license or proposed changes to the UFSAR or Bases that involve an unre viewed safety question as defined in 10 CFR 50.59 shall be reviewed and e proved by the NRC prior to implementation. implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
A change in the Technical Specifications incorporated in the license; or 2.
WATERFORD - UNIT 3                             6-26
A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
c.
The Bases Control Program shall contain provisions to ensure that the %ses are maintained consistent with the UFSAR.
d.
Proposed changes to the Technical Specifications incorporated i's the license or proposed changes to the UFSAR or Bases that involve an unre viewed safety question as defined in 10 CFR 50.59 shall be reviewed and e proved by the NRC prior to implementation. implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
WATERFORD - UNIT 3 6-26


      ~-
~-
J NPF-38-216 ATTACHMENT D COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM           i l
J NPF-38-216 ATTACHMENT D COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM
I I


                  ,                            Attcchm:nt D to W3F1-99-0111
Attcchm:nt D to W3F1-99-0111
                            , COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM
, COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM


==Subject:==
==Subject:==
Technical Specification Change Request NPF-38-216, Administrative Controls Section 6.0 Technical Specification Changes Data:           July 13,1999 SCHEDULED ONE-                     COMPLETION TIME CONTINUING             DATE(IF     ASSOCIATED COMMITMENT (S)                 ACTION COMPLIANCE             REQUIRED)       CR OR ER Establish Waterford 3 administrative               N/A         YES           Commitment       TSCR controls to process TS Bases changes in                                     25661 Prior to NPF-38-216 cccordance with requirements delineated                                       TS Change t
Technical Specification Change Request NPF-38-216, Administrative Controls Section 6.0 Technical Specification Changes Data:
in TSCR NPF-38-216.                                                         Implementation
July 13,1999 SCHEDULED ONE-COMPLETION TIME CONTINUING DATE(IF ASSOCIATED COMMITMENT (S)
                      ~
ACTION COMPLIANCE REQUIRED)
        'Ch ck o 3e only
CR OR ER Establish Waterford 3 administrative N/A YES Commitment TSCR controls to process TS Bases changes in 25661 Prior to NPF-38-216 cccordance with requirements delineated TS Change in TSCR NPF-38-216.
                    ~
Implementation t
VOLUNTARY ENHANCE'WlENT(S)                                   ASSOCIATED CR OR ER 1
~
'Ch ck o 3e only
~
VOLUNTARY ENHANCE'WlENT(S)
ASSOCIATED CR OR ER 1
l l
l l
l l
l l
l Page 1 of 1 l}}
l Page 1 of 1 l}}

Latest revision as of 16:44, 6 December 2024

Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019
ML20210D107
Person / Time
Site: Waterford 
Issue date: 07/15/1999
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20210D089 List:
References
RTR-NUREG-1432 NUDOCS 9907270130
Download: ML20210D107 (19)
v • d • e


Text

0 9

e 4

NPF-38-216 ATTACHMENT A EXISTING SPECIFICATION I

9907270130 990715 PDR ADOCK 05000382 l

P PDR

. o. -

111D11 ADMINISTRATIVE CONTROLS SECTION f, gig 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-22 6.12 HIGH RADIATION AREA........................................

6-22 6.13 PROCESS CONTROL PR0 GRAM....................................

6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PR0 GRAM...................

6-24 l

i WATERFORD UNIT 3 XVIII Amendment No. 68,124

l,q.

de l

ADMINISTRATIVE CONTROLS l

HIGH RADIATION AREA (Continued) 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 level in the area has been established and personnel have been made knowledgeable of them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) l with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.

6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mroms* but less than 500 rads" shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall I

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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrams* but less than 500 rads" that are located within large areas, such as PWR 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 waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive j

exposure control over the activities within the area.

613 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:

a.

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

1.

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

  • Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.

" Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.

WATERFORD - UNIT 3 6-23 AMENDMENT NO. 66:446,146

d ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 2.

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

applicable regulations.

b.

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

I 4

614 OFFSITE 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:

Shall be documented and records of reviews performed shall be retained as required a.

by Specification 6.10.3p. This document shall contain:

1.

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

A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l 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 PORC and the approval of the General Manager Plant Operations.

I c.

Sha!! 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.

615 CONTAINMENT I FAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment intamal pressure for the design basis loss of coolant accident, P,, is 44 psig.

The maximum allowable containment leakage rate, L., is 0.5% of containment air weight per day atP,.

WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,146

e./

CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued) e._p._.e.._

a.

Overall containment leakage rate acceptance cri:eria is 51.0 L,. During the first unit startup following each test performed in accordance with this program, the overall

{

containment leakage rate a"e:eptance criteria are 5 0.60 L, for the Type B and Type C tests and s 0.75 L, for Type A tests.

b.

Airlock acceptance criteria are:

1.

Overall air lock leakage rate is s 0.05 L, when tested at 1 P,.

2.

Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig.

I c.

Secondary containment bypass leakage rate acceptance critens is s 0.06 L, when I

tested at 1 P..

d.

Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when tested at 1 P,.

The provisions of Specification 4.0.2 do not apply to the test frequences specifed in the Containment Leskage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

WATERFORD - UNIT 3 6-25 AMENDMENT NO. 494, 138

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NPF-38-216 ATTACHMENT B PROPOSED MARKED-UP SPECIFICATION

18Df2 ADMINISTRATIVE CONTROLS SECTION pgg 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-22 6.12 HIGH RADIATION AREA........................................

6-22 5 11_ PROCESS CONTROL PR0 GRAM....................................

6-23 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-24 6.15 CONTAIMENT LEAKAGE RATE TESTING PR0 GRAM...................

6-24 l

POr

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(REM /3tlah I=dA Co N f!604ATio d (Jirk MAHA GEAA t"eJY fizo&zissA..,G-b a, n vecwcn c sMcin cArwar Msc.T co <17acc /k'o6um,,, c 2.C

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.A 7-WATERFORD UNIT 3 XVIII Amendment No. 68,124

.+ l ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 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 level in the area has been established and personnel have been made knowledgeabie of them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the actnnties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.

6.12.2 in addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose 1

greater than 1000 mroms* but less than 500 rads ** shall be provided with locked doors to prevent unauthonzed entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision /designes. Doors shall l

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 area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mroms' but less than 500 rads ** that are located within large areas, such as PWR 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 waming device, in lieu of the stay time specification 1

of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protcction procedures to provide positive exposure control over the activities within the area.

813 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:

a.

Shall be documented and records of reviews performed shall be retained as required by ";n?.rt U n5 This documentation shall contain:

1.

Sufficient information to support the change together with the appropnate analyses or evaluation justifying the change (s) and

  • Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
    • Measurement made at 1 meter from the radiation source or from any surface that the radiation penetraW Ww n,wd Le-QualQ Assu - n e e iP<c nm

~

WATERFORD - UNIT 3 3

AMENDM T NO. 66;446.146

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'.?

ADMINISTRATIVE CONTROLE l

PROCESS CONTROL PROGRAM (Continued) 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 PORC and the approval of the General Manager Plant Operations.

I l

6.14 OFFSITE 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:

Shall be documented and records of reviews performed shall be retained as required a.

by Cf,m2,6v 0.10.0f,. This document shall contain:

i 1.

Sufficient information to support the change together with the appropriate

+ke. O M df analyses or evaluations juctifying the change (s) and Assevm nCG'"'"l 2.

A determination that the change will maintain the level of radioactive effluent bc72 control required pursuant to 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

i b.

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

l 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 shallindicate the date (e.g., month / year) the change was implemented.

815 CONTAINMENT I FAKAAF RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J. Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment intamal pressure for the design basis loss of coolant accident, P, is 44 psig.

The maximum allowable containment leakage rate, L, is 0.5% of containment air weight per day atP,.

WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,146

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.T.ESI.itEi.f.8QrBAM (Continued) 1 Laakage rate w$s criteria are:

a.

Overall containment lerakege rate acceptance criteria is a 1.0 L,. During the first unit startup followmg each test perfomwd in accordance with this program, the overall I

containment leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tosts and 3 0.75 L,for Type A tests.

b.

Airlock acceptance criteria are:

1.

Overall air lock leakage rate is 5 0.05 L, when tested at 1 P,.

2.

Leakage rate for each door seat is s 0.005 L, when pressurized to 110 psig.

l l

c.

Secondary containment bypass leakage rate acceptance criteria is 50.06 L, when I

tested at I P,.

d.

Containment purge valves with resilient seals acceptance criteria is 5 0.06 L, when l

tested at1 P.

l The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisi,ons of Speedication 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

b

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L M S E FCT oa n e v,- PAGe (G-u x

l WATERFORD-UNIT 3 6 25 AMENDMENT NO. 494, 138 1

1

o.

INSERT 1 6.16

( RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM )

INSERT 2 ON NEXT PAGE (6-26) 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

1.

A change in the Technical Specifications incorporated in the license; or 2.

A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

c.

The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d.

Proposed changes to the Technical Specifications incorporated in the license or proposed changes to the UFSAR or Bases that involve an unreviewed safety question as defined in 10CFR 50.59 shall be reviewed and approved by the NRC prior to implementation.

Implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

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I b

4 4

NPF-38-216 ATTACHMENT C PROPOSED SPECIFICATION

,g.

INDEX j

ADMINISTRATIVE CONTROLS l

SECTIQN PAGE

]

1 6.11 RADIATION PROTECTION PROGM.............

6-22 1

6.12 HIGH RADIATION AREA...............

6-22 6.13 PROCESS CONTROL PROGRAM......

6-23 6.14 OFFSITE DOSE CALCULATION MANUAL.....

6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM...........,

6-24 6.16. (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM)...

6-25 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM......

6-26 1

l WATERFORD - UNIT 3 XVill AMENDMENT NO. 60,124,

l

, y

.= /

. ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

I 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 dor,e rate level in the area has been established and personnel have been made knowledgeable of 3

them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate 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 the facility Radiation Protection Superintendent-Nuclear in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems* but less than 500 rads ** shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Superintendent on duty and/or health physics supervision / designee. Doors shall remain locked except during periods of access by personnel under ar approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems* but less than 500 rads ** that are located within large areas, such as PW'R 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 waming device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillacD may be made by personnel qualified in radiation protection procedures to provide positi"a exposuro 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:

a.

Shall be documented and records of reviews performed shall be retained by the Quality Assurance Program Manual. This documentation shall contain:

  • Measurement made at 30 centimeters from the radiation source or from any surface that the radiation penetrates.
    • Measurement made at 1 meter from the radiation source or from any surface that the radiation penetrates.

WATERFORD - UNIT 3 6-23 AMENDMENT NO. 00,110,146; l

,,,,, "=.4 ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 1.

Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (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 PORC and the approval of the General Manager Plant Operations.

6.14 OFFSITE 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:

a.

Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:

1.

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

A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302,40 CFR Part 190, 10 CFR 50.36a, and Appendix l 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 PORC and the approval of the General Manager Plant Operations, 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.

6.15 CONTAINMENT LEAKAGE RATE TESTING PROGrgyl A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

WATERFORD - UNIT 3 6-24 AMENDMENT NO. 00,04,110,124,140,

..l 1

. ADMINISTRATIVE CONTROLS CONTAINMENT LEAKAGE RATE TESTING PROGRAM (Continued)

The peak calculated containment intemal pressure for the design basis loss of coolant accident, P., is 44 psig.

The maximum allowable containment leakage rate, L,. is 0.5% of containment air weight per day atP,.

Leakage rate acceptance criteria are:

a a.

Overall containment leakage rate acceptance criteria is s 1.0 L,. During the first unit startup following each test performed in accordance with this program, the overall containment leakage rate acceptance criteria ares 0.60 L, for the Type B and Type C tests and s 0.75 L for Type A tests.

b.

Air lock acceptance criteria are:

1.

Overall air lock leakage rate is s 0.05 L when tested at 2 P,.

2.

Leakage rate for each door seal is s 0.005 L, when pressurized to210 psig.

c.

Secondary containment bypass leakage rate acceptance criteria is s 0.06 L, when tested at 2 P,.

d.

Containment purge valves with resilient seals acceptance criteria is s 0.06 L, when tested ata P,.

The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

6.16 (RESERVED FOR CONFIGURATION RISK MANAGEMENT PROGRAM) l WATERFORD - UNIT 3 6-25 AMENDMENT NO. +24+38

s ADMINISTRATIVE CONTROLS 6.17 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

a.

Changes to the Bases of the Technical Specifications shall be made under appropriate administrative controls and reviews.

b.

Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

1.

A change in the Technical Specifications incorporated in the license; or 2.

A change to the UFSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.

c.

The Bases Control Program shall contain provisions to ensure that the %ses are maintained consistent with the UFSAR.

d.

Proposed changes to the Technical Specifications incorporated i's the license or proposed changes to the UFSAR or Bases that involve an unre viewed safety question as defined in 10 CFR 50.59 shall be reviewed and e proved by the NRC prior to implementation. implemented changes to the Bases not requiring prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

WATERFORD - UNIT 3 6-26

~-

J NPF-38-216 ATTACHMENT D COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM

Attcchm:nt D to W3F1-99-0111

, COMMITMENT IDENTIFICATIONNOLUNTARY ENHANCEMENT FORM

Subject:

Technical Specification Change Request NPF-38-216, Administrative Controls Section 6.0 Technical Specification Changes Data:

July 13,1999 SCHEDULED ONE-COMPLETION TIME CONTINUING DATE(IF ASSOCIATED COMMITMENT (S)

ACTION COMPLIANCE REQUIRED)

CR OR ER Establish Waterford 3 administrative N/A YES Commitment TSCR controls to process TS Bases changes in 25661 Prior to NPF-38-216 cccordance with requirements delineated TS Change in TSCR NPF-38-216.

Implementation t

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'Ch ck o 3e only

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VOLUNTARY ENHANCE'WlENT(S)

ASSOCIATED CR OR ER 1

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