Text

Proposed Tech Specs Pages,Revising TS to Clarify Several Administrative Requirements,Delete Redundant Requirements & Correct Typos
	ML20212H568
Person / Time
Site:	Limerick
Issue date:	09/27/1999
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20212H555	List: ML20212H552; ML20212H568;
References
	NUDOCS 9910010186
	Download: ML20212H568 (26)
	v • d • e

n. s-1 f.

[

i ATTACHMENT 2 LIMERICK GENERATING STATION UNITS 1 AND 2.

LICENSE CHANGE REQUEST NO. 98-03-0 ;

AFFECTED PAGES (Mark-ups) ,

UNIT 1 UNIT 2 3/4 8-16a 3/4 8-16a 3/4 8-19 3/4 8-19

&2 S2 S7 67 6-13 6-13 6-16 S16 O y

3892300520 ELECTRICAL POWER SYSTDes I

LIMITING COW ITION FOR OPERATION (Continued) b.

D.C. Power Distribution Panels 1.

Unit 1 Division 1, Consisting of:

a) 250-V DC Fuse Sox:

lk(

b) 1FA (IAD105) D 250-V DC Motor Control Cent l c) IDA (100201) 125-V DC Distribution Panels IPPA1 l l (IAD102) >

1 PPA 2 (1AD501)

, 2. Unit 1 Division 2, Consisting of: 1 PPA 3

-(1AD162)

I a) 250-V DC Fuse Sox:

b) 1FB (180105) 250-V DC Motor Control Centers: l 108-1 (100202) i c) 108-2 (100203) 125-V DC Distribution Panels: 1PPS1 (180102) 1PPS2 (180501)

3. 1PPS3 (15152)

Unit 1 Division 3, Consisting of:

l a) 125-V DC Fuse Box:

b) 1FC (ICD 105) 125-V DC Distribution Panels: 1PPC1 3 (ICD 102) '

1PPC2 (ICD 501)

4. Unit 1 Division 4, Consisting of:

l a) 125-V DC Fuse ;,x:

b) IFD (1D0105) 125-V DC Distribution Panels: 1PP01 (ID0102) 1 PPD 2 (1D0501) 1 PPD 3 i

(1D0162) 5.

Unit 2 and Connon Division 1 Consisting of: I 1

a) 250-V DC Fuse Box: 2FA b) 125-V DC Distribution Panels: (2AD105) 2 PPA 1 (2AD102) 2 PPA 2 (2A0501) 6.

Unit 2 and Common Division 2. Consisting of:

a) 250-V DC Fuse Box: 2FB (280105) b) 125-V DC Distribution Panels: 2PP81 (280102) 2PPS2 (280501) !

7. Un Common Division 3, Consisting of:

.g a) DC Fuse'8ox:

b) DC Distributio 2FC (2CD105) k '

lh 2PPCI (2CD102) B !

8. Uni Common Division 4, Consisting of:

2PPC2 (2CD501)

(

a) y DC Fuse Box: 2FD i b) DC Distribution Panels: (200105) $

2 PPD 1 (200102) 2 PPD 2 (200501)

LIE RICK - UNIT 1 3/4 6-15e Jus 22115 Amendment No. 24 )

3892300520 ELECTRICAL. POWER SYSTDtS -

1.IMITING C00eITION FOR OPERATION (Continued)

b. D.C. power distribution:

1. Unit 1 Division 1, Consisting of: ~

l a) 250-V DC Fuse Box: 1FA (1AD105) b) 250-V DC Motor Control Center: IDA (100201) c) 125-V DC Distribution Panels: 1 PPA 1 (IAD102)

IPPA2 (IAD501) 1 PPA 3 (IAD162)

2. Unit 1 Division 2, Consisting of:

a) l ;

250-V DC Fuse Box: IFB b)

(180105) 250-V DC Motor Control Centers: 108-1 (100202) i 108-2 (100203) c) 125-V DC Distribution Panels: IPP81 (18D102) 1PPS2 (180501)

3. 1PPS3 (180162)

Unit 1 Division 3, Consisting of:

a) 125-V DC Fuse Box: l 1FC (ICD 105) b) 125-V DC Distribution Panels: IPPC1 (ICD 102) 1PPC2 (ICD 501) i 1PPC3 (ICD 162)

4. Unit 1 Division 4, Consisting of:

j a) 125-V DC Fuse Box: 1FD b) 125-V DC Distribution Panels: IPPD1 ' ((100105) 100102)

IPP02 (100501) 1PP03 (1D0162)

5. Unit 2 and Common Division 1 Consisting of:

a) 250-V DC Fuse Box: 2FA b) (2AD105) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) 2 PPA 2 (2AD501)

6. Unit 2 and Common Division 2, Consisting of:

a) 250-Y DC Fuse Box: 2FB b) 125-V DC Distribution Panels: (28D105) 2PP81 (280102) 2PP82 (280501)

7. Uni Common Division 3, Consisting of:

a g

Fuse Box: 2FC b (2CD105) b) DC Distribution Panels: 2PPCI 0 (200102) ,

2PPC2 (2CD501) R j

8. Uni Common Division 4, Consisting of:

$ j a Fuse Box: 2FD (200105) b '

b) DC Distribution Panels: 2 PPD 1 (200102) % j 2 PPD 2 (200501)

LIE RICK - UNIT 1 3/4 8- 19 Jul 2 21M Amendment No. 24 l

l

ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when s fuel is in the reactor. In addition, while the unit is in ?

OPERATIONAL C0f0! TION 1, 2, or 3, at st one licensed Senior Operator shall be in the control ro N( 9

c. A Health Physics Technician

shall be on site when fuel is in the 4 reactor; %

d. ALL Cor.E ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator l Limited to fuel Handling who has no other concurrent responsibilities during this operation;

]

e. (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physi-cists, auxiliary operators, and kev =mintanance personnel).

nomma /

Adequate shift coverage sha e ned without routine heavy use of overtime. The obj ive shall be to have operating personnel D work E N t 5 40-hour week while the unit is operating. k However, in the even at unforeseen problems require substantial y amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, y3 on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding l shift turnover time.

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

The Health Physics Technician position may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided imediate action is taken to fill the required position.

DS 2 0 M LIMERICK - UNIT 1 6-2 Amendment No. M.35. 96.104

- Intu-sTIg ennfans t 6.4 TRAINIE 6.4.1 Training programs for the unit staff shall be maintained under the direction of the site training organization. The retraining and replacement training programs for all affected positions except licensed operators shall meet or' exceed the standards of. ANSI /ANS 3.1-1978. The retraining and replacement training programs for licensed operators shall comply with the requirements of 10

. CFR 55, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERAIl0NS REVIEW C0ffiITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters f related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Operations Review Committee is composed of nine regular members from the Limerick Generating Station staff. Members shall collectively have experience iin the following areas:

Plant Operations Engineering Maintenance ,

Instrumentation and Controls Planning Radiation Safety Chemistry g Experience Assessment

, h Members shall meet the requirements of ANSI /ANS 3.1-1978, Section 4.7, for the )

applicable required experie.1ce and be appointed in writing by the Plant Manager. g The Chairman and alternate iheteestof the PORC shall be drawn from the PORC members g and appointed in writing y the_PTant Manager.

ALTERNATES -

Y 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.

000 RUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

Amendment No. 10.33.55.96 LIMERICK - UNIT 1 6-7 Corrected by Letter' dated October 17, 1995

p .n n n.m u c-..n. w___ _ --

SAFETY LIMIT VIOLATION (Continued)

d. Critici operatten of the unit shall not be resumed until authorized by the Commission.

6.8 PRDCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities' referenced below:

-a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c. Refueling operations. l

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

~

~ ' ~

h. PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

J. Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, and any other b I procedure or procedure change that the Plant Manager determines to affect nuclear o safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6~, 4, 6.5.1.7 and/or 6.5.3, as appropriate, prior to isolementation. Each procedure of A Specification 6.8.1 shall also be reviewedQdig' gas set forth in &

Administrative Procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made i provided: I

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and i

c. The ch'ange is documented, reviewed by an SQR in accordance with Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

LIMERICK - UNIT 1 6-13 Amendment No. 70.#7,96 AUG 0 81995

ADMINISTRATIVE CONTROLS Allinl& LEE 20 PIX (Continued) dosimeter, thersoluminescent dosimeter (TLD), or film badge measure- '

monts. Small exposures totallin dose need not be accounted for. In g <205 of the individual the aggregate, at leasttotal 80% l of the total whole-body dose received from external sources should be assigned to specific major work functions. The report shall be $ l submitted by April 30 of eacn year. E b.

i

~% (PelehJ) ~ i

c. Any other unit unique reports required on an annual basis.

d.

The results of specific activity analysis in which the primary

{

coolant exceeded the lhits of Spec.fication 3.4.5. The following i information 48 shall hours prior be i' v.1ded: (1) Reactor power history starting to the st sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to excding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Eacn result should include date and time of sampling and the radiciodine concentrations; (3) Cleanup !

system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolanz exceeded the radioiodine limit.

_ MONTHLY OPERATING REPORTS

6.9.1.6 Routine reports of operating statistics and shutdown experience, includ-ing documentation of all cnallenges to the main steam system safety / relief valves, shall be submitteo on a monthly basis to the. U.S. Nuclear Regulatory Commission ATTN: Document Control Desk, Wasnington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.7 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 shall include summaries, interpreta-tions, ansiysis of trendt of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.S.2, IV.B.3, and IV.C of Appenoix I to 10 CFR Part 50.

i b

% singit suomTttal may te mace for a multiple unit station. M22N LIMERICV,- UNIT 1 "" m. 2 . m. E, US 6-15

.~

ILFIIRKe LPE B _IIIIEE 1

LIMITING CONDITION F08 OPE 8ATION (Continued)

b. D.C. Power Distribution Panels

1. Unit 2 Division 1 Consisting of:

a) 250-V DC Fuse Box: e 2FA (2AD105) b)

c) 250-V DC Motor Control Cent 125-V DC Distribution Panels.

20A 2 PPA 1 (200201) l[&

(2AD102) $

2 PPA 2 (ZAD501) g

2. Unit 2 Division 2, Consisting of:' N a) 250-V DC Fua Box: 2FB b) (280105) 250-V DC Motor control Centers: 2D8-1 (20D202) 200-2 (20D203) c) 125-V DC Distribution Panels: 2PP81 (28D102) i 2PPS2 (200501) 2PP83 (28D162)

3. Unit 2 Division 3, Consisting of: I a) 125-V DC Fuse Box: 2FC b) (2CD105) 125-V DC Distribution Panels: 2PPC1 (2CD102) !

2PPC2 (200501) '

4. Unit 2 Diivision 4, Consisting of:

a) 125-V DC Fuse Box: 2FD b) (200105) 125-V DC Distribution Panels: 2 PPD 1 (200102) 2 PPD 2 (200501) 2 PPD 3 (200162).

5. Unit I and Common Division 1, ConsistinC of:

a) 250-V DC Fuse Box: IFA (1AD105) b) 125-V DC Distribution Panels: 1 PPA 1 (IAD102)

IPPA2 (1AD501)

6. Unit 1 and Common Division 2, Consisting of:

a) 250-V DC Fuse Box: IF8 (18C105) b) 125-V DC Distribution Panels: IPP81 (18010?,)

IPP82 (180501)

7. Uni Common Division 3. Consisting of:

a) Fuse Box: -

IFC (ICD 105) s b) W V DC Distribution Panels: IPPCI (ICD 102) ?

1FPC2 (ICD 501) g

8. Un Common Division 4, Consisting of:

a) Fuse Box: IFD (IDL105) W b) I n-V DC Distribution Panels:

1 PPD 1 IPPD2 (10D102)

(2D0501)

(

LIIERICK - IslIT 2 3/.4 9-16e nel 2 5 W

ELECTRICAL MWEA SYSTBIS .

LIMITIE COW ITION FOR OPERATION (Continued) c) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) 2 PPA 2 (2AD501)

2. Unit 2 Division 2,. Consisting of:

a) 250-V DC Fuse Box: 2F8 b) (I20105) 250-V DC Motor Control Centers: 2D8-1 (200202) 2D8-2 (200203) c) 125-V DC Distribution Panels: 2 PPB 1 (2BD102) 2PP82 (28D501) 2PP83 (280162)

3. Unit 2 Division- 3, Consisting of: .

a) 125-V DC Fuse Box: 2FC (2CD105) b) 125-V DC Distribution Panels: 2PPCI (2CD102) 2PPC2 (2CD501) 2PPC3 (2CD162)

4. Unit 2 Division 4, Consisting of:

a) 125-V DC Fuse Box: 2FD b) (200105) 125-V DC Distribution Panels: 2 PPD 1 (20D102) 2 PPD 2 (20D501) 2 PPD 3 (20D162)

5. Unit I end Common Division 1, Consisting of:

1 a) 250-V DC Fuse Box: IFA (1 ADIOS) -

b) 125-V DC Distribution Panels: 1 PPA 1 (IAD102) 1 PPA 2 (IAD501)

6. Unit 1 and Common Division 2, Consisting of:

a) 250-V DC Fuse Box: IF8 (180105) b) 125-V DC Distribution Panels: 1PP81 (18D102)

IPP82 m'!(18D501)

7. Uni Division 3, Consisting of:

a) Fuse Box: IFC (ICD 105) g*t b) DC Distribution Panels: IPPCI (ICD 102) 0 1PPC2 (ICD 501) g

8. Unit Common Division 4, Consisting of:

a) N Fuse Box: IFD (100105) b) DC Distribution Panels: IPPD1 IPPD2

(19D102)

(1D0501)

(

EP).!CABILITY: OPERATIONAL ColeITIONS 4, 5, and *. .

j AL'."l0N:

a. With less than two divisions of the above required Unit 2 A.C.

distribution systems energized, suspend CORE ALTERATIONS, handling of

irradiated fuel in the . secondary containment and operations with a '

potentia 1 for draining the reactor vessel. l 3 .

i "When handling irradiated fuel .in the secondary containment.

LIBERICK - WlIT 2 3/4 8-19 ADE 2 i W

wi s w.. - a 6.2.2 LalIT STMF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room uhen ful {

is in the reactor. In addition, while the unit is in OPERATIo mL o ColeITION 1, 2, or at least one licensed Senior Operator shall be in the control 4 I(g

c. A Health Physics Technician

shall be on site when fuel is in the l reactor;

d. ALL CORE ALTERATIONS shall be observed and directly. supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. (Deleted) - INFORM TION FROM THIS SECTION RELOCATED TO THE TIgl.

f. Administrative procedures shall be developed and implemented to limit the workles hours of sett staff she perfors-sefety-relatzd ftmettens !

(e.g., licensed Senior Operators, licensed Operators, health physi- '

cists, auxiliary operators, and how 1-M)*enance personnel).

Cnomin< k Adequate shift coverage sha De maintained without routine heavy S use of ove . The obj ive shall be to have operating psrsonnel A work a T_._1 " 1 . ; p 40-hour week while the unit is operating. A However, in the event tnat unforeseen problems require substantial $

amounts of overtime to be used, or during extended periods of shut- g down for refueling, major maintenance, or major unit modifications, g on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

l

The Health Physics Technician position may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required position.

LIMERICK - UNIT 2 6-2 Amendment No. 2,69.68 MC 2 01995

-n aETE .I 6.4 TRAINIIIE 6.4.1 Training programs for the unit staff shall be maintained under the direction of the site training organization. The retraining and replacement training prof. -a for all affected positions except licensed operators shall meet or exceed the u,mdards of All51/AIIS 3.1-1978. The retrataing and replacement training programs for licensed operators shall comply with the requirements of 10 CFR 55, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW Als AUDIT 6.5.1 PLANT OPERATIONS REVIEW CulttITTEE (PORC)

FlK TION 6.5.1.1 The PORC shall function to advise the Plant Manager on 611 matters related to nuclear safety.

CGMPOSITION 6.5.1.2 The Plant Operations Review Committee is composed of nine regular j members from the Limerick Generattag Station staff. Members shall co.loctively j have experience in the following areas: '

Plant Operations >

Engineering i Maintenance Instrumentation and Controls Planning Radiation Safety Chemistry g Experience Assessment h Members shall meet the requirements of ANSI /ANS 3.1-1978, Section 4.7, for the i applicable required experience and be appointed in writing by the Plant Manager. D The Chairman and alternateVfM'Dof the PORC shall be drawn from the PORC members g - l and appointed in writing by the_ Plant Manager. N ALTERilATES l

6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman l to serve on a temporary basis; however, no more than two alternates shall participate-as voting members in PORC activities at any one time.

l MEETING FREQUENCY l 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate. I DUDRtr 6.5.1.5 The quorum of the PORC necessary fer the performance of the PORC .

responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including i alternates.

LIMERICK - UNIT 2 6-7 Amendment No. 2g,60 Alm 0 8 f)95 )

Wi Eummiiw ranyam t SAFFTY E M (Castimmed)

d. Critical operation of the unit shall not be resumed until authorized by

-the Commission. i 6.8 PROCEDURES MS PRDGRMtS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737 and Supplement I to NURM737.

c. Refueling operations,

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h.. PROCESS CONTROL PROGRAM implementation.

1. OFFSITE DOSE CALCULATION MANUAL implementation.

j.

Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15 February 1979.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, and any other procedure or procedure change that the Plant Manager determines to affect nuclear h safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, ?

6.5.1.7 and/or 6.5.3, as appropriate, prior to i ntation. Each procedure of Specification 6.8.1 shall also be reviewed .-.;C @ as set forth in D u,

Administrative Procedures. % N 6.8.3 Temporary changas to procedures of Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and

c. The change is documented, reviewed by an SQR in accordance with I Specification 6.5.3.1, and approved by either the Plant Manager or his destee.1ted alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

LIMERICK - UNIT 2 6-13 Amendment No. 19,60 1 AIM 0 81995 i

%u-nd. -(

AIERIAL .REPDETS (Cortinued) dosimeter, thericoluminescent dosimeter (TLD), or film badge measure-monts.

San 11 exposures totalling <205 of the individual total dose need not be accounted for. In the aggregate, at least 805

' l of the total whole-body dose received from external sources should be assigned to specific major work functions. The report : hall be k submitted by April 30 of each year. h b.

c.

~~ _ = MNS (peledeel) ,

Any other unit unique reports required on an annual basis, d.

The results of specific astivity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. Me following infor1mation shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Cleanup I system flow' history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) firaph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit. 3 MONTHLY OPERATING REPORTS

5.9.1.5 Routine reports of operating statistics and dutdown experience, includ-ing documentation of all challenges to the main staan system safety / relief valves, shall be submitted on a monthly basis to the ATTN: Document Control )4 Desk, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy ?

A to the Regional Administrator of the Regional Office of the MRC no later than the 15th of each month following the calendar month covered by the report. I 9

ANNUAL RADIOLOGICAL ENVIRolMENTAL OPERATING REPORT

6.9.1.7 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 initial report shall be schnitted prior to May 1 of the year following initial criticality. The report shall include summaries, interpretations, 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 outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

A single suosittal may be made for a multiple unit station.

JR 2 ? 195 LIMERICK - UNIT 2 6-16 Mendurit E 4. E

it b

-- ( ;

I ATTACHMENT 3 i

LIMERICK GENERATING STATION i UNITS 1 AND 2 LICENSE CHANGE REQUEST NO. 98-03-0 1 i

AFFECTED PAGES (Camera-ready)

UNIT 1 UNIT 2 3/4 8-16a 3/4 8-16a 3/4 8-19 3/4 8-19 1 6-2 6-2 l 6-7 6-7 6-13 6-13 6-16 6-16 l

1 i

7 ELECTRICAL P0ldER SYSTEMS l LIMITING CONDITION FOR OPERATION (Continued) i

b. D.C. Power Distribution Panels

1. Unit 1 Division 1, Consisting of:

a) 250-V DC Fuse Box: 1FA (IAD105) i b) 250-V DC Motor Control Center: 1DA (10D201) l l c) 125-V DC Distribution Panels: IPPA1 (1AD102) l IPPA2 (IAD501)

IPPA3 (IAD!62) l l 2. Unit 1 Division 2, Consisting of:

a) 250-V DC Fuse Box: IFB (180105) b) 250-V DC Motor Control Centers: 108-1 (100202) i 1DB-2 (10D203) I c) 125-V DC Distribution Panels: IPPB1 (18D102)

IPPB2 (180501)

IPPB3 (180162)

3. Unit 1 Division 3, Consisting of:

a) 125-V DC Fuse Box: IFC (ICD 105) i b) 125-V 2 Distribution Panels: IPPCI (ICD 102) 1PPC2 (ICD 501)

IPPC3 (ICD 162)

4. Unit 1 Division 4, Consisting of:

a). 125-V DC Fuse Box: IFD (IDD105) !

b)' 125-V DC Distribution Panels: IPPD1 (1D0102) i

~

IPPD2 (100501)

5. Unit 2 and Comon Division 1, Consisting of:

a) 250-V DC Fuse Box: 2FA (2AD105) b) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) i 2 PPA 2 (2AD501)

6. Unit 2 and Common Division 2, Consisting of: i 1

a) 250-V DC Fuse Box: 2FB (2BD105) b) 125-V DC Distribution Panels: 2 PPB 1 (2BD102) ,

J 2 PPB 2 (2B0501)

7. Unit 2 and Comon Division 3, Consisting of:

a) 125-V DC Fuse Box: 2FC (200105) j b) 125-V DC Distribution Panels: 2PPC1 (200102) 2PPC2 (200501)

8. Unit 2 and Common Division 4, Consisting of:

a) 125-V DC Fuse Box: 2FD (2DD105) l b) 125-V DC Distribution Panels: 2 PPD 1 (20D102) 2 PPD 2 (200501) l l

LIMERICK - UNIT 1 3/4 8-16a l

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

b. D.C. Power Distribution:

1. Unit 1 Division 1, Consisting of:

a) 250-V DC Fuse Box: IFA (1AD105) b) 250-V DC Motor Control Center: 1DA (10D201) c) 125-V DC Distribution Panels: IPPAl (1AD102)

IPPA2 (1AD501)

IPPA3 (IAD162)

2. Unit 1 Division 2, Consisting of:

a) 250-V DC Fuse Box: IFB (18D105) b). 250-V DC Motor Control Centers: 108-1 (10D202) 1D8-2 (10D203) c) 125-V DC Distribution Panels: IPPB1 (18D102)

IPPB2 (180501)

IPPB3 (180162)

3. Unit 1 Division 3, Consisting of:

a) 125-V DC Fuse Box: IFC (1C0105) b) 125-V DC Distribution Panels: IPPCI (1C0102)

IPPC2 (1C0501)

IPPC3 (1C0162)

4. Unit 1 Division 4, Consisting of:

a) 125-V DC Fuse Box: IFD (1DD105) b) 125-V DC Distribution Panels: IPPD1 (1DD102)

IPPD2 (IDD501)

IPPD3 (IDD162)

5. Unit 2 and Comon Division 1, Consisting of:

a) 250-V DC Fuse Box: 2FA (2AD105) b) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) 2 PPA 2 (2AD501)

6. Unit 2 and Comon Division 2, Consisting of:

a) 250-V DC Fuse Box: 2FB (28D105) l b) 125-V DC Distribution Panels: 2 PPB 1 (2BD102) l 2 PPB 2 (2BD501) l

7. Unit 2 and Comon Division 3, Consisting of:

a) 125-V DC Fuse Box: 2FC (20D105) l b) 125-V DC Distribution Panels: 2PPC1 (20D102) <

8. Unit 2 and Comon Division 4, Consisting of:

a) 125-V DC Fuse Box: 2FD (200105) l b) 125-V DC Distribution Panels: 2 PPD 1 (2DD102) 2 PPD 2 (200501)

LIMERICK - UNIT 1 3/4 8-19 k

.)

l

,, ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when

. fuel is'in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room; l

c. A Health Physics Technician

shall be on site when fuel is in the.

reactor;

d. ALL CORE AL1ERATIONS shall be observed and directly supervised by either a. licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; I

e. (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

l

f. Administrative procedures shall be developed and implemented to limit the working hours of uit staff who perform safety-related functions .

(e.g., licensed Senior Operators, licensed Operators, health physi-cists, auxiliary operators, and key maintenance personnel). ,

1 Adequate shift coverage shall be maintained without routine heavy )

use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week.while the unit is operating. l However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelites shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift. ,

The Health Physics Technician position may be less than the minimum requirements i for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected i absence, provided immediate action is taken to fill the required position.

LIMERICK - UNIT 1 6-2 x_

ADMINISTRATIVE CONTROLS 6.4 TRAINING i

6.4.1 Training programs for the unit staff shall be maintained under the direction of the site training organization. The retraining and replacement training programs for all affected positions except licensed operators shall meet or exceed the standards of ANSI /ANS 3.1-1978. The retraining and replacement training programs for licensed operators shall comply with the requirements of 10 CFR 55, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters

, 'related to nuclear. safety.

COMPOSITION l

6.5.1.2 The Plant Operations Review Committee is composed of nine regular members from the Limerick Generating Station staff. Members shall collectively have experience in the :

following areas:

{

Plant Operations Engineering-Maintenance Instrumentation and Controls Planning Radiation Safety Chemistry Experience Assessment Members shall meet the requirements of ANSI /ANS 3.1-1978, Section 4.7, for the applicable required experience and be appointed in writing by the Plant Manager.

The Chairman and alternate Chairmen of the PORC shall be drawn from the PORC members l and appointed in writing by the Plant Manager.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as' voting members in PORC activities at any one time.

MEETING FREQUENCY

-6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the ,

PORC Chairman or his designated alternate. i OVORUM !

6.5.1.5 The quorum of the PORC necessary for the performance of the PORC )

responsibility and authority provisions of these Technical Specifications shall '

censist of the Chairman or his designated alternate and four members including alternates.

LIMERICK - UNIT 1 6-7

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

d. Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737.

c. Refueling operations.

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

1. OFFSITE DOSE CALCULATION MANUAL implementation.

j. Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, and any other procedure or procedure change that the Plant Manager determines to affect nuclear safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, as appropriate, prior to implementation. Each procedure of Specification 6.8.1 shall also be reviewed as set forth in l Administrative Procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered; I

b. The change is approved by two members of the unit management staff, at i least one of whom holds a Senior Operator license on the unit affected; I and j

c. The change is documented, reviewed by an SQR in accordance with Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification 6.1.1, or the Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation.

l LIMERICK - UNIT 1 6-13

ADMINISTRATIVE CONTROLS

~ ANNUAL REPORTS (Continued) dosimeter, thermoluminescent dosimeter (TLD), or film badge measure-ments. Small exposures totalling <20% of the individual total dose need not be accounted for. In the aggregate, at least 80%

of the total whole-body dose received from external sources should be assigned to specific major work functions. The report shall be submitted by April 30 of each year.

b. (Deleted)

c. Any other unit unique reports required on an annual basis.

d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration {

and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity l i

above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORTS

4 6.9.1.6 Routine reports of operating statistics and shutdown experience, includ-hng documentation of all challenges to the main steam system safety / relief valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory C.ommission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy

o the Regional Administrator of the Regional Office of the NRC no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.7 The Annual Radiological Environmental Operating Report covering the 1 operation of the unit during the previous calendar year shall be submitted 1 before May 1 of each year. The report shall include summaries, interpreta- l tions, analysis of trends of the results of the Radiological Environmental l Monitoring Program for the reporting period. The material provided shall be i censistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

l

'A single submittal may be made for a multiple unit station.

LIMERICK - UNIT 1 6-16

f.~_

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

b. D.C. Power Distribution Panels

1. Unit 2 Division 1, Consisting of:

a) 250-V DC Fuse Box: 2FA (2AD105) b) 250-V DC Motor Control Center: 2DA (20D201) l c) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) 2 PPA 2 (2AD501) 2 PPA 3 (2AD162)

2. Unit 2 Division 2, Consisting of:

a)- 250-V DC Fuse Box: 2FB .(280105) b) 250-V DC Motor Control Centers: 208-1 (20D202) 2DB-2 (20D203) c) 125-V DC Distribution Panels: 2 PPB 1 (2BD102) 2 PPB 2 (2BD501) 2 PPB 3 (28D162)

3. Unit 2 Division 3, Consisting of:

a) 125-V DC Fuse Box: 2FC (200105) b) 125-V DC Distribution Panels: 2PPC1 (200102) 2PPC2 (200501) 2PPC3 (200162)

4. Unit 2 Division 4, Consisting of:

a) 125-V DC Fuse Box: 2FD (20D105) b) 125-V DC Distribution Panels: 2 PPD 1 (200102) 2 PPD 2 (2DD501) ;

2 PPD 3 (200162)

5. Unit I and Comon Division 1, Consisting of:

i a) 250-V DC Fuse Box: IFA (IAD105) j b) 125-V DC Distribution Panels: IPPAl (IAD102) 1 PPA 2 (IAD501)

6. Unit 1 and Comon Division 2, Consisting of:

a) 250-V DC Fuse Box: IFB (180105) o) 125-V DC Distribution Panels: IPPB1 (1BD102)

IPPB2 (1B0501)

7. Unit 1 and Comon Division 3, Consisting of:

a) 125-V DC Fuse Box: IFC (ICD 105) l b) 125-V DC Distribution Panels: IPPCI (100102)

IPPC2 (ICD 501)

8. Unit I and Comon Division 4, Consisting of: l a) 125-V DC Fuse Box: IFD (10D105) l b) 125-V DC Distribution Panels: IPPD1 (10D102)

IPPD2 (100501)

LIMERICK - UNIT 2 3/4 B-16a

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) c) 125-V DC Distribution Panels: 2 PPA 1 (2AD102) 2 PPA 2 (2AD501) 2 PPA 3 (2AD162) s

2. Unit 2 Division 2, Consisting of:

a) 250-V DC Fuse Box: 2FB (2BD105) b) 250-V DC Motor Control Centers: 2DB-1 (20D202) 2DB-2 (20D203) c) 125-V DC Distribution Panels: 2 PPB 1 (2BD102) 2 PPB 2 (2BD501) 2 PPB 3 (2BD162)

3. Unit 2 Division 3, Consisting of:

a) 125-V DC Fuse Box: 2FC (20D105) b) 125-V DC Distribution Panels: 2PPC1 (20D102) 2PPC2 (200501) 2PPC3 (2CD162)

4. Unit 2 Division 4, Consisting of:

a) 125-V DC Fuse Box: 2FD (200105) b) 125-V DC Distribution Panels: 2 PPD 1 (2DD102) 2 PPD 2 (200501) 2 PPD 3 (2DD162)

5. Unit I and Common Division 1, Consisting of:

a) 250-V DC Fuse Box: IFA (1AD105) l b) 125-V DC Distribution Panels: IPPA1 (1AD102)

IPPA2 (1AD501)

6. Unit I and Common Division 2, Consisting of:

a) 250-V DC Fuse Box: IFB (18D105) b) 125-V DC Distribution Panels: IPPB1 (1BD102)

IPPB2 (IBD501)

7. Unit I and Common Division 3, Consisting of:

a) 125-V DC Fuse Box: IFC (ICD 105) l b) 125-V DC Distribution Panels: IPPCI (1C0102)

IPPC2 (ICD 501)

8. Unit I and Common Division 4, Consisting of:

a) 125-V DC Fuse Box: IFD (1D0105) l b) 125-V DC Distribution Panels: IPPD1 (1DD102)

IPPD2 (IDD501)

APPLICABILITY: OPERATIONAL CONDITIONS 4, 5, and *.

ACTION: l

a. With less than two divisions of the above required Unit 2 A.C.

distribution systems energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

When handling irradiated fuel in the secondary containment.

LIMERICK - UNIT 2 3/4 B-19 j

ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF i

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room; l

c. A Health Physics Technician

shall be on site when fuel is in the reactor;

d. ALL CORE ALTERATIONS shall'be observed and directly supervbed by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; ]

)

e. (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM. I

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physi-cists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a nominal 40-hour week while the unit is operating. l However, in the event that unforeseen problems require substantial .

amounts of overtime to be used, or during extended periods of shut- '

down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, all excluding shift turnover time.

"The Health Physics Technician position may be less than the minimum requirements fcr a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill the required position.

LIMERICK - UNIT 2 6-2

I ADMINISTRATIVE CONTROLS 6.4 TRAINING 6;4.1 Training programs for the unit staff shall be maintained under the direction of the site training organization. The retraining and replacement training programs for all affected positions except licensed operators shall meet or exceed the standards of ANSI /ANS 3.1-1978. The retraining and replacement training programs for licensed operators shall comply with the requirements of 10 CFR 55, and shall include familiarization with relevant industry operational experience.~ -

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMITTEE (PORC1 FUNCTION 605.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.

LQMPOSITION 6.5.1.2-The Plant Operations Review Committee is composed of nine regular members from.the Limerick Generating Station staff. Members shall collectively have experience in the following areas:

Plant Operations Engineering Maintenance Instrumentation and Controls Planning Radiation Safety Chemistry Experience Assessment Members shall meet the requirements of. ANSI /ANS 3.1-1978, Section v.7, for the applicable required experience and be appointed in writing by the Plant Manager.

The Chairman and alternate Chairmen of the PORC shall be drawn from the PORC members l and appointed in writing by the Plant Manager.

ALTERNATES 6.5.1.3 - All alternate members shall be appointed in writing by the PORC Chairman

'to serve on 'a temporary basis; however, no.more than two alternates shall participate as voting members in PORC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate.

DUORUM 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his' designated alternate and four members including alternates.

LIMERICK - UNIT 2 6-7

i ADMINISTRATIVE CONTROLS I SAFETY LIMIT VIOLATION (Continued) d.- Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained

' esvering the activities referenced below:

a. The' applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737.

c. Refueling operations.

-d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

1. OFFSITE DOSE CALCULATION MANUAL implementation.

'j. Quality Assurance Program for effluent and environmental *nitoring, using the guidance of Regulatory Guide 4.15, February 1979.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, and any other procedure or procedure change that the Plant Manager determines to affect nuclear safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, as appropriate, prior to implementation. Each procedure of Specification 6.8.1 shall also be reviewed as set forth in l Adainistrative Procedures.

6.8.3 . ' Temporary changes to procedures of Specification 6.8.1 may be made provided:

a. The intent of the original procedure is not altered;

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; i and

c. The change is documented, reviewed by an SQR in accordance with .

Specification 6.5.3.1, and approved by either the Plant Manager or his i designated alternate in accordance with Specification 6.1.1, or the ;

Director or Manager designated by Administrative Procedures as the responsible Director or Manager for that procedure within 14 days of implementation. !

LIMERICK - UNIT 2 6-13

p l

l ADMINISTRATIVE CONTROLS l

ANNUAL REPORTS (Continued) dosimeter, thermoluminescent dosimeter (TLD), e film badge measure-ments. Small exposures totalling <20% of the individual total dose need not be accounted for. In the aggragate, at least 80%

of the total whole-body dose received from external sources should be assigned to specific major work functions. The report shall be submitted by April 30 of each year.

b. (Deleted) l l

c. Any other unit unique reports required on an annual basis.

d. The results of specific activity analysis in which the primary

. coolant exceeded the limits of Specification 3.4.5. The following information shall be included: (1) Reactor power history starting {

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was f exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in {

which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The tin,e duration when the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORTS

6.9.1.6 Routine reports of operating statistics and shutdown experience, includ-ing documentation of all challenges to the main steam system safety / relief valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6.9.1.7 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 initial report shall be submitted prior to May 1 of the year following initial criticality. The report shall inc'lude summaries, interpretations, 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 outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

u ,n l

A single submittal may be made for a multiple unit station.

LIMERICK - UNIT 2 6-16

ML20212H568

Text

Navigation menu

Search