ML20217B268

Proposed Rev D to ITS

ML20217B268
Person / Time
Site:	Byron, Braidwood
Issue date:	02/14/1998
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20217B265	List: ML20217B259 ML20217B268
References
NUDOCS 9803250476
Download: ML20217B268 (52)

Text

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Attachment q

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Improved Technical Specifications (ITS)

Revision D Affected Page List and Instructions SECTION/ TAB REMOVE REV. A/B (PAGE) INSERT REV. D (PAGE) 5.0 BYRON ITS 5.0-10 5.0-10 5.0-44 5.0-44 5.0-47 5.0-47 5.0-48 5.0-48 X 5.0-48a 5.0 BRWD ITS 5.0-10 5.0-10 5.0-44 5.0-44 5.0-47 5.0-47 5.0-48 5.0-48 X 5.0-48a em 5.0 BYRON CTS MARKUPS 3/4 6-10 3/4 6-10 C INSERT 3.6-10A/B 6-20 INSERT 3.6-10A/B 6-20 X INSERT D 6-23 6-23 INSERT 6-23A INSERT E 6-25 6-25 INSERT 6-25A/B INSERT 6-25A/B 6-26 6-26 j X INSERT 6-26A  ;

5.0 BRWD CTS MARKUPS 3/4 6-10 3/4 6-10 INSERT 3.6-10A/B INSERT 3.6-10A/B 6-20 6-20 X INSERT D 6-23 6-23 INSERT 6-23A INSERT E i 6-25 6-25 )

INSERT 6-25A/B INSERT 6-25A/B 1 6-26 6-26 X INSERT 6-26A

'5.0 CTS DOCS 5.0-8 5.0-8 X 5.0-8a X 5.0-8b 5.0-9 5.0-9 p

LJ 1 L 9903250476 980224 '

DR ADOCK 050004

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l Attachment O'

Improved Technical Specifications (ITS)

. Revision D Affected Page List and Instructions SECTION/ TAB REMOVE REV. A/B (PAGE) INSERT REV. D (PAGE) 5.0 LC0 MARKUPS 5.0-10 5.0-10 5.0-23 5.0-23 5.0-24 5.0-24 INSERT 5.0-24A INSERT 5.0-24A/b 5.0-25 5.0-25 X INSERT 5.0-25A 5.0 LC0 JFDs 5.0-5 5.0-5 (3.

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Enclosure I O

ITS Revision D l

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I Organization-5.2-5.2 Organization- (continued) 5.'2.2 Facility Sta'ff .

The facility staff organization shall-include the followingi a, A total of three non-licensed operators for the two units is required in all conditions. At least one-of the required non-licensed operators shall be assigned to each unit.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(1) and 5.2.2.a and 5.2.2.f

.for a period of' time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

'c A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken.to fill the required position.

d. The amount of overtime worked by unit staff members performing safety related functions shall be limited and O controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).

e. The operations manager or the supervisor in charge of the operations shift crews shall hold an SRO license.

f. The Shift Technical Advisor (STA) shall provide advisory l technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the facility. .In addition, the STA shall meet the qualifications specified by the Commiss' ion Policy Statement on Engineering Expertise on Shift.

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N BYRON'--UNITS 1.& 2. 5.0-3 2/14/98 Revision D e

Programs and Manuals 5.5

(] 5.5 Programs and Manuals (continued)

\J 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Proaram This program provides controls for monitoring'any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies and acceptance criteria shall be in general conformance with requirements of 10 CFR 50.55a(b)(2)(vi), 10 CFR 50.55a(b)(2)(ix). ASME Boiler and Pressure Vessel Code Subsection IWL. 1992 Edition with the 1992 Addenda and Regulatory Guide 1.35.1. July 1990.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pumo Flywheel Insoection Procram This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14. Revision 1. August 1975.

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BYRON - UNITS 1 & 2 5.0-10 2/14/98 Revision D

Reporting Requirements 5.6 (3 5.6 Reporting Requirements (continued)

G 5.6.8- Tendon Surveillance Reoort Any abnormal degradation of the containment structure detected during the tests required by'the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI 1992 Edition with the 1992 Addenda.

5.6.9 Steam Generator (SG) Tube Insoection Reports

a. Following each inservice inspection of SG tubes, the number of tubes plugged or repaired in each SG shall be reported to the NRC within 15 days.

b. The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection. The report shall include:

)

1. Number and extent of tubes inspected.

2. Location and percent of wall thickness penetration for each indication of an imperfection, and

(

) 3. Identification of tubes plugged or repaired.

c. Results of SG tube ins)ections that fall into Category C-3 shall be reported to tle NRC within 30 days and prior to resumption of unit operation. The report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

f~') (continued)

V BRAIDWOOD - UNITS 1 & 2 5.0-44 2/14/98 Revision D

High Radiation Area 5.7 5.0 ADMINISTRATIVE. CONTROLS 5.7 - High Radiation Area

'This Specification provides alternate methods for controlling access to high_

radiation areas and does not apply to very high radiation areas as defined in 10 CFR 20.-

5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c). in lieu of the requirements of 10 CFR 20.1601. each high radiation area, as defined in 10 CFR 20. in which the intensity of radiation is

-- > 100 mrem /hr but s 1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by

. requiring issuance of a Radiation Work Permit (RWP) or equivalent document that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation protection equipment and measures. Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates s 1000 mrem /hr. provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset-integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

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, L6 (continued)

BYRON - UNITS 1-& 2 5.0 2/14/98 Revision D

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.High Radiation: Area- I 5.7 j

'5.7 High Radiation _ Area

5. 7.1 ' (continued)-

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c. An individual 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 in the RWP or equivalent document,

.~5.7.2' .In addition to the requirements of Specification 5.7.1, areas accessible to personnel with radiation levels > 1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates shall require the following:

a. Doors shall be locked to prevent unauthorized entry and shall'not prevent individuals from leaving the area. In place of locking the door, direct or continuous electronic surveillance that is capable of detecting unauthorized entry may be used. The keys shall be maintained under the l administrative control of the Shift Manager on duty or

= health physics supervision; q b. Personnel access and exposure control requirements of g activities being performed within these areas shall be  !

specified by an approved RWP or equivalent document that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation

. protection equipment and measures;

c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter). Surveillance and radiation monitoring by health physics personnel may be substituted for an alarming' dosimeter:

d. For individual high radiation areas accessible to personnel with radiation levels of > 1000 mrem /hr at 30 cm (12 inches) that are located within large areas such as reactor containment, where no enclosure exists for pur)oses of locking, and where_no enclosure ~can be reasona)1y.

constructed around the individual area that individual area shall be barricaded, conspicuously posted, and a flashing l'- light shall be activated as a warning device: and 1

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'(continued)

BYRON M UNITS (1L& 2' 5.0-48 2/14/98_ Revision D

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High Radiation Area 5.7

() 5.7 High Radiation Area 5.7.2 (continued)

e. Except for individuals qualified in radiation protection procedures, or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas.

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1 7-BYRON - UNITS 1 & 2 5.0-48a 2/14/98 Revision D

t Organization 5.2 5.2 Organization' (continued) 5.2.2 ~ Facility Staff

.The_ facility staff organization shall include the following:

ca. A~ total of three non-licensed operators;for the two units is' required in all. conditions. At least one of the' required non-licensed operato s shall be assigned to each un_it.

b. Shift-crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(1) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of _on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

_c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more

-than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. The amount of overtime worked by unit staff members performing safety related functions shall be limited and controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).

e. The operations manager or the supervisor in charge of the operations shift crews shall hold an SR0 license. -

f. The Shift Technical Advisor (STA) shall provide advisory

] technical support to the Shift Manager in the areas of thermal hydraulics. reactor engineering. and plant analysis with regard to the safe operation of the facility. In addition. the STA shall meet the qualifications specified by the Commiss' ion Policy Statement on Engineering Expertise on Shift.

)

'BRAIDWOOD -'_ UNITS'1 & 2: 5.0-3 2/14/98 Revision D t

Programs and Manuals 5.5 (7 5.5 Programs and Manuals (continued)

V 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Proaram This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies and acceptance criteria shall be in general conformance with requirements of 10 CFR 50.55a(b)(2)(vi), 10 CFR 50.55a(b)(2)(ix). ASME Boiler and Pressure Vessel Code Subsection IWL 1992 Edition with the 1992 Addenda and Regulatory Guide 1.35.1. July 1990. In addition.

Unit 1 may have sheathing filler grease voids in excess of 5% of the net duct volume for up to 35 tendons until the end of A1R07.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pumo Flywheel Insoection Procram This program shall provide for the inspection of each reactor 6 coolant pump flywheel in general conformance with the Q recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14. Revision 1. August 1975.

l Il

,g V (continued)

BRAIDWOOD - UNITS 1 & 2 5.0-10 2/14/98 Revision D J

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

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' 5 '. 6. 8 ' Tendon Surveillance Reoort Any abnormal ~ degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported-in the Inservice-Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI,-1992 Edition with the 1992 Addenda.

5.6.9 Steam Generator-(SG) Tube Insoection Reoorts

a. Following each inservice inspection of SG tubes, the number e of tubes plugged or repaired in each SG shall be reported to the NRC within 15 days.

, b. The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection. The report shall include:

1. Number and extent of tubes inspected,

2. Location and percent of wall thickness penetration for each indication of an imperfection, and O 3. 1eent4f4 cat 4en ef tebe n,ve9ee er rene4 red.

c. Results of SG tube ins)ections that fall into Category C-3 shall be reported to tie NP,C within'30 days and prior to resumption of unit operation. The report shall provide a

' description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

. 1

O (continued)

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BYRON - UNITS 1 & 2- 5,0-44 2/14/98 Revision D

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High Radiation Area 5.7'

'5.0 . ADMINISTRATIVE CONTROLS

-5.7 High Radiation Area This Specification provides alternate methods for controlling access to high radiation areas and does not apply to very high radiation areas as defined in

.10'CFR 20. -

5.7.1 Pursuant to 10 CFR 20. paragraph 20.1601(c), in lieu' of the requirements of 10 CFR 20.1601. each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is

> 100 mrem /hr but s 1000 mrem /hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation.

penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by.

requiring issuance of a Radiatio, Work Permit (RWP) or equivalent document that includes specification of radiation dose rates in the immediate work area (s)-and other appropriate radiation protection equipment and measures. Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates s 1000 mrem /hr provided

~ they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

(continued)

.BRAIDWOOD - UNITS 1 & 2 5.0-47 2/14/98 Revision D Y'

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High Radiation Area-5.7 5.7 ~ High ' Radiation . Area 15.7.1: - (continued) .

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c. An in'dividual 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 in the RWP or equivalent document.

5,7. 2 - - In addition to the requirements of Specification 5.7.1. areas

' accessible'to personnel with radiation levels >.1000 mrem /hr at.

30 cm (12. inches) from the. radiation source or from any surface which the radiation penetrates shall require the following:

a, ' Doors shall be locked to prevent unauthorized entry and shall not prevent individuals from leaving the area. In place of locking the door, direct or continuous electronic surveillance that'is capable of detecting unauthorized entry-may be used. The keys shall be maintained under the l administrative control of the Shift Manager on. duty or health physics supervision;

p b. Personnel access.and exposure control requirements of t activities being performed within these areas shall be specified by an approved RWP or equivalent document that includes specification of radiation dose rates in the immediate work area (s) and other a protection equipment and measures:ppropriate radiation

- c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter). Surveillance and radiation monitoring by health-physics personnel may be substituted for an alarming dosimeter:

d. For individual high radiation areas accessible to personnel.

with radiation levels of > 1000 mrem /hr at 30 cm (12 inches) that are located within large areas such as reactor containment, where.no enclosure exists for pur>oses of

. locking, and where no enclosure'can be reasona)ly.

constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing

.l ~ light shall be activated as a warning device: and (continued)

IBRAIDWOODi- UNITS 1 & 2 L5.0-48 2/14/98 Revision'D

( i

High Radiation Area 57

('~' 5.7 High Radiation Area D) 5.7.2 (continued) .

e. Except for individuals qualified in radiation protection procedures, or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of then. Individuals escorted will receive a pre-job briefing prior to entry into such areas.

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~.,s Y' BRAIDWOOD - UNITS 1 & 2 5.0-48a 2/14/98 Revision D i

j LCO .3 (o, j l 5 au L +,u 5.e M TAINMENT SYSTEMS SURVE s E REQUIREMENTS (Continued) f y -

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v 4.6.1.6.2 End Anchora_ s and Adiacent Concrete Surfac s. The structural integrity of the end anch' es of all tendons inspected pursuant to Specifi-cation 4.6.1.6.1 and the adja t concrete surffces shall be demonstrated by determining.through inspection t at no apparint changes have occurred in the visual appearance of the end anchora'gep the concrete crack patterns adjacent to the end anchorages since last inspecte(. Inspections of the concrete shall H

be performed during the containmen't vessel Te don tests (reference Specifica-tion 4.6.1.6.1). /

/

4.6.1.6.3 Containment-Vessel Surfaces. The structura integrity of the exposed accessible interior and exterior surfaces of the tainment vessel, including the,1-iier plate, shall be determined during the shu wn for each Type A containment leakage rate test (reference Specification 4. . .2) by a visual 'nspection of these surfaces. This inspection shall be perfo d prior to ype A containment leakage rate test to verify no apparent chang 'n earance or other abnormal degradation.

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"~'r BYRON - UNITS 1 & 2 3/4 6-10

CTS INSERT (S)

SECTION 5.0 Byron Specification 5.5.6 l INSERT 3.610A (Asa . Au and LAg) 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Proaram This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment. structural integrity. The program shall include

- baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in general conformance with requirements of 10 CFR 50.55a(b)(2)(vi), 10 CFR 50.55a(b)(2)(ix). ASME Boiler and Pressure Vessel Code Subsection IWL 1992 Edition with the 1992 Addenda and Regulatory Guide 1.35.1. July 1990.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

O -l INSERT 3.610B (An and LAp )

5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected dur_ing the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI. 1992 Edition with the 1992 Addenda.

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2/14/98 Revision D Y

ADMINISTRATIVE CONTROLS

3. M INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued) m .RESPONSIBILI b 6.2.3.3 The ISEG shall onsible for maint ' g surveillance of plant l activitics to provide indepen nt erifica that these activities are performed correctly and that human e are reduced as much as practical.

RECORDS 6.2.3.4 Rec of activities performed by the ISEG shall epared, main-f tained forwr.rded each calendar month to the Site Quality Veri tion ctor, and the Station Manager, Byron Station.

(5, 2. f SHIFT TECHNICAL ADVIS0g

.5224 The Shift Technical Advisor shall provide advisory technical support to the ShiftEn-ineer;in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the facility.

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.-h BYRON - UNITS 1 & 2 6-2a AMENDMENT NO. 75

3puu h. 5.o ADMINISTRATIVE CONTROLS O PRDCEDUBES AND PROGRAMS (Continued)

N) 2 Men (UseCensustoensurethatchangesin use of areas at and bey he SITE BOUNDARY are identif d and that modifica-tions to the ring progr made if required by the results of this can

3) Partici that ' patiendent achecks Interlaboratory rison Program to ensure on the precis o accuracy of the surements of radioactive materials in envi tal sample matrices are performed as part of the quality assura rogram for environmental monitoring. _ m 56 E B REPORTING REQUIREMENTS e '

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.sh.u h .suL. AJ m 1 I"00:=. ::.r;;u ) $ oc w J Lii m.g wak ryto.,+,cu so4. (

[6.v.A in = .... t; the maaiicable reporting requiremente of Federal Regulations, the'follaw'aa af Title 10, t. ode Lhac"h=ittedtotheRegional}

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i Adminic+eter ;f ;.;= nm, Regional Office,. . . ...::unless otherwise notea. 1.

D RTUP REPORT ,

i 6.9.1. summary report of plant startup and power escalation testin all be submitt following: (1) receipt of an Operating License (2) nt to the license lying a planned increase in power level, (3} in lation of O fuel that has a erent design or has been manufactured by differer.. fuel supplier, and (4) no ' ications that may have significant altered the nuclear, thermal, or hydraulic pe ormance of the plant.

6.9.1.2 The Startup Report sh address each the tests identified in the Final Safety Analysis Report FSAR shall

• clude a description of the measured values of the operating conditions or eteristics obtained during the test program and a comparison of these va s 'th design predictions and specifica-  !

GA- tions. Any corrective actions th were req ' d to obtain satisfactory opera- l tion shall also be described. y additional s ific details required in license conditions based o her commitments shal included in this report.

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6.9.1.3 Startup Re s shall be submitted within: (1)9 s following com-plation of the 5 tup Test Program, (2) 90 days following re tion or com-  !

mencement of rcial power operation, or (3) 9 months followi initial criticali , whichever is earliest. If the Startup Report does not er all three nts (i.e.,' initial criticality completion of Startup Test P , and

,reJs ar tion or commencement of commercial operation) supplementary reports s 1  !

)( sumiitted at least every 3 months until all three events have been complete .

5.I..l l-tr-9-E+J Annual Reports covering the activities of t Q g,. I A"il 50 as(describedbelow for the previous calendar year shall be submitted prior to rr I of each Of

/The ini ... ..,,,,.. ...... I "vear.

": vin: i.-iti:1 :-itic:lity. 1

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BYRON - UNITS 1 & 2 6-20 AMENDMENT NO. 50 '

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Containment Vessel Structural Intenrity Pronram N Q g.

This program provides contr sfor uding

- routine inspections and' degradation tests to id' and monitoring corrective actioncontainment

~ vessel stru radation is found.

The Containment Vessel Structural Int Program,inspecti uencies, and acceptance

. criteria shall be in accordance with 10 CFR 50';55a(b ," Effective edition and addenda of

~

Subsection IWE and Subsection IWL, Sect on- 10 CFR 50.55a(bX2Xix)," Examination

. of concrete containments," as y approved exchptions. Predicted tendon lift-off forces - ,

t with the recommendations of R'egulatory Guide 1.35.1, July 1990.

shall be determinedjco '

In addition,

• i may have sheathing filler grease voids in excess o}5% of the net duct volume fo 5 tendons until the end of BIR08.

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ACTIBCALITYANALYSISOFBYRONANDBRAIDWOODSTATIONFUELSTDRAGERAC

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O 6.9.1.10 Fue documented in the.

STORAGE RACKS. The anal chment limits for storage shall be establis LITY ANALYSIS OF BYRON AND BRAI methods used to de nd STATION FUEL the maximum fuel /j

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enrichments shall be those prev

" CRITICALITY ANALYSIS OF BYRON AND 8 revi DOO!

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ISTATION FUEL STORAGE RACKS."_. \

The g ! appro fuel enrichment limits for stora 1, mined so that all applicable j Z Ay limits (e.g., subcriticalit the safety ana are met. / s The CRITICA LYSIS OF BYRON AND BRAIDWOOD STAT L STORAGE k

" " 3 N ot0 RACKS repo all be provided upon issuance of any cha s, to RC -

' Doc ontrol Desk, with copies to the Rggional Admin trator and f a

. Dector. A A w '

5 IAL RE Ao 4 /m . 9. 2 Speci reports s all be s ttad to Regio'n Administ ator of e

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C Regional Office wit in the ti period s cified fo each rep rt. ,

i 1 10 RECORD RETENTION

, n addition to the applicable record retention requirmeents of Title 10 i

.- Code ederal Regulations, the following records shall be retained for a least t inimum period indicated.

6.10.1 The flowing records shall be retained for at least 5 years-

a. Reco and logs of unit operation covering time inte at each power le  ; -

b. Records and s of principal maintenance activi es, inspections, ,

repair and rep ement of principal items of ipment related to nuclear safety;

c. All REPORTABLE EVENT ,

d. Records of surveillance ivities, spections, and calibrations required by these Technical ci cations;

e. Records of changes made to cedures required by LA Specification 6.8;

f. Records of radioactive ipments;

g. Records of sealed s rce and fission det r leak tests and results; and

h. Records of an al physical inventory of all se d source material of record. ,

6.10.2 The folio ng records shall be retained for the duratio of the unit Operating Lice  : i a.* R ords and drawing changes reflecting unit design modifica ons i de to systems and equipment described in the Final Safety lysis I Report;

b. Records of new and irradiated fuel inventory, fuel transfers and

~ h - y aur_nus' histories; o 6-23 Q MENgENT NO. 50 Rev.D  ;

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Replorect wiih Inc.er+ 3. 6 -lob

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Os ONTAINME SSEL STRUCTURAL INTEGRITY REPORT -

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6.9.1.11 Any abnormal degradation the co ent structure detected during the tests 'N

. required by the Contai essil1! structural Integrity Program shall be rep

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NRC wi The report shall incIu'desdescription of the tendon condition, the <

' on of the concrete (especially at tendon ancTW' rages), the inspection procedures, ,

s the tolerances on cracking, and the corrective action en.

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By ( 6. - 23)

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! high ra$hohon arcos and does ne+ occN b very hinh rerhM ieri orenc m Spe,. A,.m s . o I defined in locrw 20. I 9

s OA'ADMINISTRATIVECONTROLSO^ 4' * " " " * 'd '

5/7 5 2 HIGH RADIATION AREA 4

g 20.H.OllcT h lI 30 cm O2 ird.< d j/ zo

/

5.7.1 6-9-w Pursuant to Paragraph =.=f:1fD of 10 CFR Part 20,lin lieu of the

" control device" or "alars signal" required by parag,raph '*". "'2f 2, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radia-tion is equal to or less than 1000 mR/hr ath = = in.)lfrom the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Pemit (RWP), Individuals qualified in radiation protection procedures or personnel continuously escorted 34,. mim '

by such individuals may be exempt from the RWP issuance requirement during the ; dou- w performance of their assigned duties in high radiation areas with exposure rates f equal to or less than 1000 mR/h, provided they are otherwise following plant Ce ^l l-radiation protection procedures for entry,into such highe radiation areas. Any individual or group of individuals oemitted to enter such areas shall be pro-vided with or accompanied by one or more of the following: l

a. .'A radiation monitoring. device which continuously indicates the radiation dose rate in the area; or i

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alams when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or

c. An individual 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 CI.nsed G-25Q specified in the Radiat4cn Work Permitarequiv.iee4 4ec. ,n41 A

y Nee r r b e e ,o 02 ue x,, jj j 5.u it u.a In addition to the requi(rements of Specif~ication f.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at C s 00 in.) from the radiation source or from any surface which the radiation penetrates shall be provided witt@ocked doors to prevent unauthorized entrLana T.ne Keys shall be maintained under the admini rative control of the Shift (Feaeman90n duty and/or @# ^l c health physics supervision. b oors shall remain locked except durino periods of  :

access by personnel under an approved RWPAW:: :=:: :p :ny in d::: r:T.e . or e,q v,o u j levels in t: C .... -. k-erees-end-the-eaximum-ell-:rdl; ;tay-time-for m 4 c o-*

4ndivid=1: in th:t :res. In lier ef-the-stay ti:: :

direct-or =n-te (4uch :: :!:: d :ie: it W nea:) pcification ef-the-RWP~

eentitrus-surve441ance  !

may be de by perseaaa! geel" fed 4" *edietien-pratedier pnocedur.e te p-avide ,

p=iti= ::;:: r: ::nt=1 :=r th ::tiviti : Min p:rf:rnd eithi- th :=:.

Aring .nr;;;;3 :itz:ti;= di:h i=:l= p:n==I inj j :: ::ti;= th: 2 pr:=nt :jer :;;i;r nt t 3:, ::: tinter: ::=:ill:::: =d r:dicti= ncitring of th: = rk : :: b : cc:44fied-individual-may-be-subst4tuted-for-th: :: tin:

"'" . arou Lie.l d$ccibon d rod ahon doze rot en (In s er + k .25 8) that inclu.le in O .e m n uM}ece, es meoc N W der q9topnate gnm+ 3 ) o rathQk Rh M VII-I 3k eChoO CYYI#

BYRON - UNITS 1 & 2 6-25 AMENDMENT NO. 50

CTS INSERT (S)

SECTION 5.0 Specification 5.7

l. INSERT 625A (A and L2 )

3 and shall not prevent individuals from leaving the area. In place of locking the door, direct or continuous electronic surveillance that is capable of

-detecting unauthorized entry may be used INSERT 6 25B (L2 )

c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter). Surveillance and radiation monitoring by health physics personnel may be substituted for an

[ alarming dosimeter:

O

. )

gs ~

2/14/98 Revision 0

%ecdua W 5.o ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 5.7..?.JFor individual high radiation areas accessible to personnel with radiation  !

. levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded (4 s a ;d = ..ti;.1 2;tal- th;; 9 0 ,

conspicuously posted, and a ashi light shall be activated as a warning 9 devicex jand ornmn.-z Aq MS y 6 1 PROCESS CONTROL PROGRAM (PCP) 6.13.1 s to the PCP:

a. Shall be unented and records.'of reviews perfo shall be retained as ired by Specification 6.10.2o ibis documentation shall contain:

1) Sufficient informati os rt the change together with the appropriate analyses or uations justifying the change (s) and,

2) A determina that the change will tain the overall confo of the solidified waste produ o existing re nts of Federal, State, or other appl le regulations.

b. become effective after review and acceptance by the 'te Review and Investigative Function (Onsite Review) and the appro of the Station Manager.

5,r.l.e,JFFF10FFSITE DOSE CALCULATION MANUAL (ODCM) p-m-N Changes to the ODCM: ,-

5.5.1. c.. I p. Shall be documented and records of reviews perfonned sha15 be

--':mec :: - :rt .. _, ,.;t 'istic . 5.10. 0;) This documentation shall contain: '

5.5.l.c.l.i # Sufficient infomation to support the change together with the appropriate analyses or evaluations justifying the change (s) and, 5.fi.l.c.l.ti & A determination that the change will maintain the level o llo1 %

-radioactive affluent control required by 10 CFR 20 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

~

' E.5. l. c. 2 g. Shall become effective after !;;t;L : d n;Gt:nce h the 0xit#

(";;icu ::d In;;;tig;tiv; Functi:n : dithe annroval of the Itation O knaad^^'"'^'^^^^^'**^'""^^~"^^^'^^^^^^'^~^^^^

D ;ti:2.l SYRON - UNITS 1 & 2 6-26 AMENDMENT NO. 50

CTS INSERT (S)

SECTION 5.0

. Specification 5.7

. INSERT 6 26A .(A,3 and M,)

e. Except for individuals qualified.in radiation protection procedures, or personnel escorted by such individuals, entry into such areas shall be

. made after dose rates in the area have been determined and entry personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas.

e O

. e' 2/14/98 Revision D

LCO 34.l Spuliw 5.o CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. . 6. 2 End Anchorages and Adjacent Concrete Surfaces. The structur integr1 f the end anchorages of'al-1 tendons inspected pursuant to 4 cifi-cation 4.6. . I and the adjacent concrete surfaces shall be d strated by determining thro inspection that no apparent changes h occurred in the visual appearance o end anchorage or the concre rack patterns adjacent to the end anchorages sin ast inspected. Ins ions of the concrete shall be performed during the contal t vessel on tests (reference Specifica-tion 4.6.1.6.1).

k 4'.6.1.6.3 Containment Vessel exposed accessible inter' faces. The ructural integrity of the

'and exterior surface the containment vessel, including the liner e, shall be determined during shutdown for each Type A containe eakage rate test (reference Specificat 4.6.1.2) by a visual ins ion of these surfaces. This inspection shall be formed prior to the e A containment leakage rate test to verify no apparent c s in a rance or other abnormal degradation.

S Y. L , "ITuss (2.7 .3. b - # o A O

5.b.8 .ThntRJ .T. b so s y 4

U BRAIDWOOD - UNITS 1 & 2 3/4 6-10 -

2 7 l 0

CTS INSERT (S) l, SECTION 5.0

. Braidwood Specification 5.5.6 l INSERT 3.610A (Au Au. and LA3 )

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Proaram- -

This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments. _ including effectiveness of its corrosion protection medium to ensure

- containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon-

, Surveillance Program, inspection frequencies..and acceptance criteria shall be in general conformance with requirements of ..

10 CFR 50.55a(b)(2)(vi) 10 CFR 50.55a(b)(2)(ix). ASME Boiler and Pressure Vessel Code Subsection IWL. 1992 Edition with the 1992 Addenda arid Regulatory Guide 1.35.1 . July 1990. In addition.

Unit 1 may have sheathing filler grease voids in excess of 5% of the net duct volume for up to 35 tendons until the end of A1R07..

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

O l INSERT 3.6 10B (Aeand LAa) 5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI. 1992 Edition with the ~992 Addenda.~

aU 2/14/98 Revision D m.q.t r4 e

'#d 'a 5 0 ADMINISTRATIVE CONTR0ts h INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued) d RESPONSIBILI 6.2.3.3 The ISEG shall sponsible for mai ng surveillance of plant l activities to provide indepen verific that these activities are performed correctly and that human'e are reduced as much as practical. )

l RECORDS 6.2.3.4 Rec of activities performed by the ISEG shall $r tained forwarded each calendar month to the Site Qualityrification Ve'epared, main-D or, and the Station Manager, Braidwood Station. N

( 5. 2. e 5MIP ItcM':ICAL ADVISOR) 5.2.2.fThe Shift Technical Advisor shall provide advisory technical support to the Shiftansineer'in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the facility. O (ManQger )

o

\

i b W W 4 W W f BRAIDWOOD - UNITS 1 & 2 6-2a AMENDMENT NO. 67

spec,LT, e 9.0 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

O 2 at Land Use Census to ensure that changes modifica yond the SITE BOUNDARY ar to the monito e use of areas ntified and that program are made if required by the results o sus, and

3) Partici n in a Interlabor Comparison Program to e that independent checks on t ision and accuracy of the measurements of radioactive materia nvironmental sample matrices are perfomed as part of the qual assurance program for environmentQJeonitorjng._ o S.(c 4 ?) REPORTING REDUIREMENTS b ""

(The Joll.m.',,, reporb .sh.n b .sul.4 4) i" A' M s arelente Joh to C90. SD A .

~

i 6.9 In 1 tion o the 'licabl reporti g requ ements f Titi 10, Co o Feder egul ions, t foll ng repo s shal be su itted the egional ini rator the N Region Offic unless therwi e noted i M TARTUp REPORT 6.9.1. A summary report of plant startup and power escalation testin shall be sube d following: (1) receipt of an Operating License. (2) nt to the license volving a planned increase in power level, (3) ins lation of -

fuel that has ifferent design or has been manufactured by different fuel supplier, and (4) difications that may have significant1 a'tered the O nuclear, thermal, or draulic performance of the plan 6.9.1.2 The Startup Repor hall address each o e tests identified in the j Final Safety Analysis Report R and shall i ude a description of the 8 _, measured values of the operating ndition r characteristics obtained during ,

the test program and a comparison o values with design predictions and I specifications. Any corrective acti s at were required to obtain I satisfactory operation shall also e descr d. Any additional specific details required in license c stions based other commitments shall be included in this report.

6.9.1.3 Startup Rep s shall be submitted within: (1 0 days following com-pletion of the St up Test Program, (2) 90 days following sumption or com-mencement of c rcial power operation, or (3) 9 months fol ing initial criticality ichever is earliest. If the Startup Report does t cover all three ev s (i.e., initial criticality, completion of Startup Test gram, and r umption or commencement of commercial operation) supplementary orts s be submitted at least every 3 months until all three events have be omoleted.

5.G.I 4;FEW. Annual Reports covering the activities of the facility as described l below for the previous calendar year shall be submitted p_rior to ?2- of each year. g l

BRAIDWOOD - UNITS 1 & 2 6-20 AMENDMENT NO. 59

h Regicaced wd h Insert 3 6-loa (g. Com=

s[

ant Va==a! Structural Intenrity Program N

This program provides contr routine inspections and tests to id or monitoring containment vessel stru egradation and correct' integrity including ctions if degradation is found.

)

\,~The Containment Vessel Structural Integn , ogram, i 'on frequencies, and acceptance.

'teria shall be in accordance with 10 CFR 50.5 vi), " Effective, edition and addenda of Subsection IWE and Subsection IWL, MS .on XI," and 50.55a(b)(2)(ix)," Examination ,

of concrete containments," as modiAM by approved exemptions. 'eted tendon lift-off forces shall be determined consi 'ith w the ecommendations r ofRegulatory e 1.35.1, July 1990.

\~ In addition, Unit ve sheathing filler grease voids in excess of 5% of duct vol6me

[or up to 3 ons until the end of A R07.

u m__- As -

4 O o U

k e

e W e' 4

?J 9

arcl (G-%

~

ap d ,.ce er.o p C'20STRATHE CGKTROLS - m N -- .

l v e v A dtMRALITY ANALYSIS OF BYRON AND BRAIDWOOD STATION FUEL STORAGE RACK O i 6.9.1.10 Fue documented in the STORAGE RACKS. The"ana richment limits for storage shall be establis CALITY ANALYSIS OF SYRON AND BRAI 1 methods used to date ATION FUEL the maximum fuel N

enrichments shall be those p sly reviewed approved by the NRC in

" CRITICALITY ANALYSIS OF BYRON AND ATION FUEL STORAGE RACKS." The / t fuel enrichment limits for storage termined so that all applicable See 4% limits (e.g., suberiticality The CRITICALI e safety a is are met. (

{3

"

• RACKS report ALYSIS OF BYRON AND BRAIDWOOO STA be provided upon issuance of any chan s, EL STORAGE 4

l NRC 'j I Documen trol Desk, with copies to the Regional Admin strator n nt Inspecy. A A ,

SPidIA M d5 .9 Ao i 9. 2 Sp fal report shall be itted to Regio 1 Adminis ator of e NRC Reg nel Office ithin the ime period pecified or each ort. v 1 10 RECORD RETENTION n addition to the applicable record retention requirements of Title .

. Code o Federal Regulations, the following mcords shall be retained to at least th inimum period indicated. ,

6.10.1 The 11owing records shall be retained for at least 5 ye s: ,

a. Recor and logs of unit operation covering time in al at each P power le 1;

b. Records and gs of principal maintenance act ties, inspections, ,

repair and rep cement of principal items o equipment related to nuclear safety;

c. All REPORTABLE EVE

d. Records of surveillance tivities inspections, and calibrations required by these Technica Spe ications;

e. Records of changes made to rocedures require'd by l Specification 6.8; I

f. Records of radioactiv hipments;

g. Records of sealed urce and fission ector leak tests and results; and

h. Records of a ual physical inventory of all aled source material of record.

6.10.2 The foil ng records shall be retained for the dur ion of the unit Operating Lice e:

a. Records and drawing changes reflecting unit design modi cations ace to systems and equipment described in the Final Safe Analysis Report;

b. Records of new and irradiated fuel inventory, fuel transfers an assembly burnup histories;

.. BRAIDWOOD - UNITS 1 & 2 h 6-23 ~,._3#

AMENDMENT NO. 39 l

m. . , .

e

.__ ..a

. , ....,.i-m ,.7 &s g,y, o O

w ,,,,, eas~m -- -

fi'epl aced wilh Insert 34 -lob 4NSERT CONTAINMENT VESSEL f M CRURAL INTEGIGTY REPORT

,7  %

'N' if 6.9.1.11 Any abnonnal degradation of the co structure detected during the tests required by the Containment tructural'IntegrigProgram shall be reported to the report shall include a desenption of the tendon condition, the

] NRCconditi within 30 da concrete (especially at tendon anchorages), the Enspection procedurps,

+

• I

+

d O

i k

e i

se O -

. Brd ( $ - 23)

.,,s e na.. u m :., uneo .ar e o x i i.m +o r cont rolh n

. ( oreoc and doec r Id ot9 vt 4e varv high.ELdiohon creac oc dd.ned in socdO -accect b han radmmn o -

, 3p1e.i h esahe* n 50 h_

. k' uAsu o%< wise s+efed

," ' ADMINISTRATIVE CONTROLS' J ac er. un i a )I E.7dPB9 HIGH RADIATION AREA

+-

,, a. W g 1 (2,.u.o0-Q

. o /

5.7.1 GED Pursuant to Paragraph -" ;- :: m, of 10 CFR Part 20,An lieu of the

" control device" or " alarm signal" required by paragra>h 22. -- :::. each high radiation area, as_ defined in 10 CFR Part 20, in which the intensity of radia-tion is. equal. to or less than 1000 mR/hr at = -- na " M from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)y anaiviouais gc t a'

qualified in radiation protection procedures or personnel continuously escorted Wai-4 by such' individuals may be. exempt from the RWP issuance requirement during the d* *** H performance .of their assigned duties in high radiation areas with exposure rates *

• equal;to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be pro- '

vided with or accompanied by one or more of the following:

s. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or t c.. An individual 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 frecuencyGwh25D specified in the Radiation Wo Permittervi .s, +w ol _

h uer] 130 c,a 02 6 Wsil i S.7.2. 4:W:# In addition to the requirements f Specification 0.12.1 larea< meressible to personnel with radiation levels greater than 1000 mR/h atli5 r '1? 'r d from the radiation source or from any surface which the radiati on penetrates shall be provided witlColocked doors to prevent unauthorized entr3i, anc tne keys shall be maintained under the admini trative control of the Shift (ForemaMon duty and/or health ohvsics supervision.6 oors shall remain locked except durino periods of

' access by personnel under ari anoroved RWP9f ch th:!' :;xify tt; d;n 7;;; O h,.a ,,,,4 '1:=1; 5 th: ' :di;t: ;;rt r:= =d th: rin : ;1 h nil; ;t;3 ti.;. fer ,.

ndbid & '- th:t rr. Ir '!: Of th: :t:y ti= :;nif f = tin ;f th; "/", .

v dir::t :r r i t: (trh = :!:rd cincit " : rn) ratin ::: :Crei' ? rr 4 ey be ede by ;- r r' ='"f ed " ndf atic: ;ntatin pandern te pre id;

ithe r;ren entre' :=r the ethitir brin; ;rfrnd af th' th: rn.

"r# ; nr;=; ;itutka chi;h I .=in F7nr.nl ir.j 7, 7,7 ntien.1;%;n te

rrat ejer ; i; rt d  ; , cr-ther

c rx i'! r n = d =di:ti n xitrin; f -th a;rt == ty ; ;=11fi:d 'ndhid=1 => b; ;;b; tit;;;d f;r the r;;tir.;

~2" ;;r;=i -;. _

.( Znser4 6-A5 8) ih04 M d ud**L thedftcailon el lodtattu) do:e roica. Q in

• he in.mdi:n e ver h or e.dc) m \ d Ler o >

&p tcprinic s amween wurina . e BRAIDWOOD.- UNITS 1 4 2 6-25 AMENDMENT NO. 39 .

CTS INSERT (S)

SECTION 5.0

. Specification 5.7.

+

l .JNSERT 6 25A (A and L2 )

3 and shall not prevent individuals from leaving the area.. In place of locking the door, direct or continuous electronic surveillance that 1s capable of detecting unauthorized entry may be used INSERT 6 25B (L2)

c. Each person. entering the area shall be provided with an alarming radiation monitoring device.that continuously integrates the radiation dose rate-(such as an electronic dosimeter). Surveillance and radiation monitoring by health physics personnel may be substituted for an I alarming dosimeter:

.=

'"'- 2/14/98. Revision D

SpeiA N s.o ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 57.2.1 For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas such as PWR containment, where no enclosure exists for purposes of locking, gand where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded - --- - '-^- ' ' '- '- " - rr?:),

conspicuously posted, and a fl hing ight shall be activated as a warning ~Q devicet j ondfome G-M A M S tE M3 PROCESS CONTROL PROGRAM (PCP) 6.13.1 es to the PCP:

a. Shall b (ocumented and records of reviews perfo d shall be -

retained as7 uired by Specification 6.10.2 . This documentation shall contain:

1) Sufficient 'infonna

• to ort the change together with the appropriate analyses o aluations justifying the change (s) and, -

2) A determin ' n that the change wi intain the overall confo '

e of the solidified waste pro to existing re ements of Federal, State, or other app

• able regulations.

b. 11 become effective after review and acceptance by the site O. Review and Investigative Function (Onsite Review) and the app 1 of the Station Manager.

5.5.l.c_ A 0FFSITE 005E CALCULATION MANUAL (ODCM) ud Changes to the ODCH:

.E.5.1. c . l s. Shall be documented and records of reviews performed shall be.

rete:n:: ;;; 7: ;r2: :. :::: ::::::: 1 = rni This docunentation shall contain:

I I.l. e.l. L .PT Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and*

5.5. l . c . l . U. El Adeterminationthatthechangewillmaintainthelevelfof linol)-h radioactive effluent control required by 10 CFR 20 6 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent,

, dose, or setpoint calculations.

5.5.l.c.2. Af . Shall become effective after/r:; ice ::d ::::;t:::: W t'.: Or.;ite; j l":;i:; =d Irt::tig:tir: F ::ti:n rdfthe ap>roval of the3(tation- .pg mananer5: th; d:t: :;::i'i:d by th: Oncit: ?:rin Orc Irrert!;etw:)-

. ::ti: l

. BRAIDWOOD - UNITS 1 & 2 6-26 AMENDMENT NO. 39 -

1 CTS INSERT (S)

SECTION 5.0 specification 5.7

~

IJgERT 6 26A (A43 and M4 )

e. Except for individuals qualified in radiation protection procedures. or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of them. Individuals escorted will receiye a pre-job briefing prior to entry into such areas.

9 uO i

.p 1/ 2/14/98 Revision D c .

DISCUSSION OF CHANGES TO CTS ITS SECTION 5.0 ADMINISTRATIVE CONTROLS Au The requirements for the Containment Vessel Structural Integrity

- Specification (CTS LC0 3.6.1.6) are placed in a program in the Administrative Controls Chapter (ITS Specification 5.5.6. " Pre-Stressed Concrete Containment Tendon Surveillance Program"). The ventilation filter testing requirements for the Control Room Ventilation System Specification (CTS LC0 3.7.6), the Nonaccessible Area Exhaust Filter Plenum Ventilation System Specification (CTS LCO 3.7.7), and the Fuel Handling Building Exhaust Filter Plenum Specification (CTS LCO 3.9.12) are placed in a program in the Administrative Controls Chapter (ITS Saecification 5.5.11. " Ventilation Filter Testing Program (VFTP)").

As suc h a statement of applicability of SR 3.0.2 and SR 3.0.3 is needed to clarify that the allowances for surveillance frequency extensions do apply, since these SRs are not normally applied to frequencies ,

identified in the Administrative Controls Chapter of the Technical Specifications. Since this change is a clarification needed to maintain provisions that would be allowed in the LC0 sections of the Technical Specifications, it is considered administrative.

A3 Various ventilation filter testing requirements of CTS LCOs 3.7.6.

3.7.7. and 3.9.12. specify that testing be performed in accordance with Regulatory Guide 1.52. Revision 2. Regulatory Guide 1.52. Revision 2.

references that testing be performed in accordance with the applicable sections of ANSI N510-1975. However, the CTS Bases for LCOs 3.7.6.

O 3.7.7. and 3.9.12 state that ANSI N510-1980 will be used as the procedural guidance for these surveillance tests. Consistent with the current licensing basis, the reference to ANSI N510-1980 has been added to the ITS Specification 5.5.11 requirements for performance of testing in accordance with Regulatory Guide 1.52. Revision 2. This change does not involve a technical change (either actual or interpretational) to the TS. As a result, this change considered to be administrative.

An By letter dated June 17. 1997. Comed submitted a CTS License Amendment Request to add testing and reporting requirements per the applicable 10 CFR 50.55a regulations and Comed committed ASME Addenda for the Pre-Stressed Concrete Containment Tendon Surveillance Program. Comed has recently updated our commitment with respect to the subject Code requirements, requiring ITS to be revised as contained in this submittal. The clouded portions of the markup (CTS 6.8.4 and CTS 6.9.1)  !

reflect this request. Any revisions to the request as a result of the conversion to ITS are annotated and justified separately. This is an administrative change with no impact on safety because the annotations

-are consistent with a CTS request. based on approved NRC regulation, for revision under NRC review.

BYRON /BRAIDWOOD UNITS 1 & 2 5.0 8 2/14/98 Revision D

DISCUSSION OF CHANGES TO CTS-ITS SECTION 5.0 ADMINISTRATIVE CONTROLS An ITS Specification 5.7.1 (CTS 6.12.1) discusses requirements for high

. radiation areas. Per recent discussions with the NRC reviewer, the following statement has been added "This Specification provides alternate methods for controlling access to high radiation areas and does not' apply to very high radiation areas as defined in 10 CFR 20."

This statement is for clarity and does not change any requirements or the methods on how high radiation areas are treated in the 31 ant. Since no changes in intent or technical requirements were made, t11s change is considered to be administrative.

An ITS 5.7 (CTS 6.12) has been revised as follows. ". . . that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation protection ecuipment and measures." This statement has been discussed and approvec by the NRC reviewer. This statement was added strictly for clarification. Since no changes in intent or technical requirements were made, this change is considered to be administrative. ,

An ITS 5.7.2.e (CTS 6.12.2) has been added and states. "Except for individuals qualified in radiation protection procedures. or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of them." This statement has been discussed and approved nv by the NRC reviewer. This statement was added strictly for clarification. Since no changes in intent or technical requirements were made, this change is considered to be administrative.

Au ITS 5.5.6 (CTS 6.8.4.g) provides basic requirements for the Pre-Stressed Concrete Containment Tendon Surveillance Program. The ITS Revision A Program required that the Tendon Surveillance Program, inspection frequencies, and acceptance criteria be in general conformance with Regulatory Guide 1.35. Revision 3. April 1979 and proposed Regulatory Guide 1.35.1. A)ril 1979. Due to the new requirements of 10 CFR 50.55a.

this statement 1as been revised to state. "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in general conformance with requirements of 10 CFR 50.55a(b)(2)(vi),

10 CFR 50.55a(b)(2)(ix). ASME Boiler and Pressure Vessel Code Subsection IWL. 1992 Edition with the 1992 Addenda and Regulatory Guide 1.35.1.

July 1990." This change is considered to be administrative since the change involves stating specific requirements that Comed has previously been committed to.

l~' . .

S  ; .l BYRON /BRAIDWOOD UNITS 1 & 2 5.0 8a 2/14/98 Revision D

DISCUSSION OF CHANGES TO CTS

(')

v ITS SECTION 5.0 - ADMINISTRATIVE CONTROLS An ITS 5.6.8 (CTS 6.9.1.11) provides basic requirements for the Tendon Surveillance Report. The ITS Revision A Program required that any degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete. Containment Tendon Program be reported to the NRC within 30 days. It further required that the report include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages) the inspection procedures, the tolerances on cracking, and the corrective action taken. Due to the new requirements of 10 CFR 50.55a. this statement has been revised to state. ". . . shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XI. 1992 Edition with the 1992 Addenda." This change is considered to be administrative since it is required for consistency with ITS 5.5.6. ITS Revision D.

g V

. c~

V l BYRON /BRAIDWOOD UNITS 1 & 2 5.0 8b 2/14/98 Revision D

DISCUSSION OF CHANGES TO CTS-ITS SECTION 5.0 ADMINISTRATIVE CONTROLS TECHNICAL CHANGES RELOCATIONS (R)

None.

TECHNICAL CHANGES MORE RESTRICTIVE (M)

M3 Not used.

Hz -CTS Section 6 has been revised to add a TS Bases Control Program description (ITS Specification 5.5.14) and a Safety Function Determination Program description (ITS Specification 5 5.15). The TS bases control program is arovided to denote the ap3ropriate methods and reviews necessary for a clange to the TS bases. T1e Safety Function Determination Program is provided to support im)1ementation of the support system Operability characteristics of t1e TS. The addition of these requirements represent a more restrictive change and is consistent with NUREG-1431 with the editorial addition to the Bases Control Program of "as modified by approved exemptions." The editorial addition is for consistency with other NUREG presentations.

M3 CTS SR 4.7.6.e.1) SR 4.7.7.d.1), and SR 4.9.12.d.1) require the performance of a pressure drop test across the combined HEPA filter and O charcoal adsorber banks of the associated ventilation systems. ITS Specification 5.5.11.d requires the same testing to be performed, but 3rovides that the testing be performed in general conformance with Regulatory Guide 1.52. Revision 2. and ANSI N510-1980. These requirements are in addition to those in the CTS, and thus represent more restrictive changes necessary to help ensure the associated ventilation systems are maintained Operable.

M, ITS 5.7.2.e (CTS 6.12.2) has been revised to state. "... entry personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas." This is considered to be a more restrictive change since the CTS does not recuire a pre-job briefing prior to entry into such areas. This adcitional requirement has been discussed with the NRC reviewer. It was confirmed with the NRC staff that the intent is to only require an informal pre-job briefing and not require any documentation which would be subject to an audit.

BYRON /BRAIDWOOD UNITS 1 & 2 5.0 9 2/14/98 Revision D

Organizaticn 5'. 2 O. 5.2 Organization Fae; Uh) b 5.2.2 Staff (continued)

~

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in an 7 day period, all excluding shift turnover time;

3. %reak of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowe etween wof eriods, including shift turnover ti ,

4. Except ing extended shutdown perio , the use of overtime s uld be considered on an dividual basis b and not for Y e entire staff on a ift.

Any deviation from th above guide nes shall be authorized

- in advance by the [ Plan uperi ndent) or his designee, in accordance with approved a i 'strative procedures, or by higher levels of management n accordance with established procedures and with docum tat n of the basis for granting the deviation.

Controls shall be cluded in the pro dures such that individual overt' e shall be reviewed thly by the [ Plant

/~T Superintendent or his designee to ensure at excessive V hours have above gui been assigned. Routine devia 'on from the ines is not authorized.

0.B The amount of overtime worked by unit staff members d- performing safety related functions shall be limited and M h _,

controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).

[-Mr suouvw .n chess. d k oswa% sumrus) h e.h The%,perations )(anager ort ^n' t:nt q: r ::ent'.:nagere O

shall hold an SR0 license. S

.dsh;4+ E.,.c.m /Monager 4, ). The Shift Technical Advisor (STA)..shall provide advisory $

technical support to the p '? inerrv urr tiinin the areap 52 of thermal hydraulics, reactor engineering, and plant (C.1:M analysis.with regard to the safe operation of the di!EW. In i addition, the STA shall meet the qualifications specified by ]

the Commission Policy Statement on Engineering Expertise on  !

Shift.

)

O O

WOG STS 5.0-4 Rev 1, 04/07/95

l Programs and Manuals 5.5 V.

5.5 '>rograms and Manuals 5.5.4 Radioactive Effluent Controls Procram (continued)

i. Limitations on the annual and quarterly doses to a member of the public from fodine-131, fodine-133,,t'ritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and J. Li.nitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit 3.9 h This program provides controls to track theCdF AR, Section4 g cyclic and transient occurrences to ensure that components are maintained within the design limits. ]

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Procram This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include Og, baseline measurements prior to initial operations. The Tendan j Surveillance Program, inspection frequencies. and acceotancelc /

criteria shall be in crerrd2% witht'" ;;;i ate. .r

^u .a 1.2,

, p.a . _ _ ~ c --- w E4 lh ;"'i $\$ Y .N ne provis1on:, or sK s.u.z and SR 3.0.3 are applicable to the o

~

Tendon Sur eillance Program inspection frequencies. -

g ras c e i s.o-my Bioid wood only J 5.5.7 Reactor Coolant Pumo Flywheel Inspection Procram  !

This program shall provide for the inspection of each reactor fm ,

h coolant pump flywheel Athe recommendations of Regulatory 88_)

Position c.4.b of Regulatory] Guide 1.14, Revision 1, August 1975.

l (mgewalc.4,-u_4h) un emenk. of locFRCo.55a (LX ZHvi), locFR ED.55ci(bX?.M tX), O i

A ME Eoiler 'ord Ff er.:.ure Veccel Corle. Subsedian IW L ,19 9 2. Eddion wit h j

+he 092 Acidendo and CC (continued) j WOG STS- 5.0-10 Rev 1, 04/07/95

LC0 INSERT (S)

/'~N SECTION 5.0 L]

. Braidwood Specification 5.5.6

~

INSERT 5.0 10A (84 )

In addition, Unit 1 may have sheathing filler grease voids in excess of 5% of the net duct volume for up to 35 tendons until the end of A1R07.

t O

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2/14/98 Revision D

~

Reporting Requirements 5.6

( 5.6 Reporting Requirements (continued)

. 5.6 Tendon Surveilfance Report Any abnormal degradation of the containment structure detected duringthetestsrequiredbythePre-[tressedConcreteContainment-Tendon Surveillance Program shall be reported to the "RC within 30 day:. The report shal' %clude a dercriptier of the t:nder candition, the cenditier of th: concrete (0:peci:lly :t tender p-

[ g anchcr:ge:), the in:pecti:n prc: d re:, th: tol cr: ::: en g cr : king, :nd th: : rrecti'/ Octi:n t: hen. t x

E 5.6 SteamGeneratorlTubeInspec ecorts -j__

a. -

^

iewer's Note: Reports required by the Licensee's current licen basis regarding steam generator tube surveill requiremen 11 be included here. An appropr' .

administrative con format should be .

• • • )

~

Reviewer's Note: These r s ma required covering a uAg -

inspection, test, alntenance activi These reports are determined o individual basis for each uni their

[  : prepa n and submittal are designated in the Techni cifications.

in Se Intervice Tnepechon Summary Repor+ in accordance udh 10CFR CO.55a and ASME Sechon XI, g3g Edihen wdh ne 0 g

iH2 Acljenda.

h

L("]

WOG STS 5.0-23 Rev 1, 04/07/95

7c.

cam 5 begswggnogproAcc; hgh radio}ico crearciTen urened nnd &r: ineticdt, orcht % wrvery wen50u i raMohen area; o; de6ned p i sur#,4e ' g High Radiation Area} (

I4 iCKFR 2.C.

H ,f J5.7}.g g 5.0 ADMINISTRATIVE CONTROLS a+ 3 o cm M inca.A b 4e_ y 0 yES.7 High Radiation Area h raba.%*n s. orts. oe 4w w sudeae.

[ 'Mw & ram.Ma pa W Pursuant to 10 CFR 20, paragraph 0.1601(c), in lieu of the 5.7.1 requirements of 10l CFR 20.1601, ach high radiation area, as i

defined in 10 CFR 20, in which t e intensity of radiation is l

> 100 mrem /hr but g,_ 000 mrem /h shall be barricaded and I

conspicuously pos as a high radiation area and entrance thereto shall be _ controlled by requiring issuance of a Radiation Work or'9"'#*'*"+ Permit (RWP)l. Individuals qualified in radiation protection

1. • "~'"f ' procedures ne.c. . Mea!n amcr Ter9irim]) Tor personnel o hno.ne) continuously escorted by such individuals may be exempt from the 3 l RWP issuance requirement during the performance of their assigned y l Pg duties in high radiation areas with exposure rates 5 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one er more of the Q following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

O A radiation monitoring device that continuously integrates b.

V the radiation dose rate in the area and alarms when a preset g l integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate o./ levels in the area have been established and personnel are l aware of them.

c. An individual 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 = :'

Or m a n en "rciecu en n = ;crh in the RWPgh' * **'*~ **w ~ n l Ja4 .3 0 <m h z iac hn ) 4~.,he raJ.a u

\ sauer.e or 4ren, anv sse ha r wkah M radMon used

(*''YO;' g 9***'g/

5.7.2 In addition to the requirements /of Specification 5.7.1. areaslwith

. 7 radiation levelsh 1000 mrem /hrJhhall be provided with 1 W con uarded doors to prevent unauthe ry and the keys shall be mai er th s rative control of the

. Shift Foreman en dut ervision. Doors shall i remain loc during periods of access el under

- oved RWP that shall specify the dose rate levels in

~"'

[L ser4 5.o-24 AJ (continued) 3

' (O WOG STS 5.0-24 Rev 1, 04/07/95

i

~

LCO INSERT (S)

(v )

SECTION 5.0 Specification 5.7 l INSERT 5.0 24A (P . P , and P i ,)

3 33 shall require the following:

a. Doors shall be locked to prevent unauthorized entry and shall not prevent individuals from leaving the area, in place of locking the door, direct or continuous electronic surveillance that is capable of detecting unauthorized entry may be used. The keys shall be maintained under the administrative control of the Shift Manager on duty or health physics supervision;

b. Personnel access and exposure control requirements of activities being performed within these areas shall be specified by an approved RWP or equivalent document that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation protection equipment and measures:

c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter). Surveillance and radiation p monitoring by health physics personnel may be substituted for an

() l alarming dosimeter; 1

INSERT 5.0 24B (P19 )

that includes specification of radiation dose rates in the immediate work area (s) and other appropriate radiation protection equipment and measures ,

l g

i  ;

s 2/14/98 Revision D

,c

,f t,

figh Radiation Area} A-

)5. 7-}a-Il O

G p{5.7 High Radiation Area].a 5.7.2 (continued) -

ediate work areas and the maximum allowable stay or individua ose areas. In lieu of the sta

._ specification of t irect or re uch as closed circuit Q TV cameras) continuous surve qualified in radiat may be made by personnel ection proie h s Jp provide positive exposure r over the activities being per 6'med-within the f.f d d. For individual _ high radiation areastwith radiation levels of

> 1000 mrem /hrkraccessible to personneU/that are located within 43 "'"

large areas such as reactor containment, where no enclosure exists 0 2 .., A,5b} for purposes of locking, Or th:t :::::t be centinurr:1y ;;rrded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and-conspicuously posted, and a flashing light shall be activ;ated as a 9

_, warning deviceX j and (-ane s.o-25 _

~

'O l

l l

l O

WOG STS 5.0-25 Rev 1, 04/07/95 .

i

.c

/

j a

LC0 INSERT (S)

SECTION 5.0

[}

. Specification 5.7.2 '

l INSERT 5.0 25A (P3 )

e. Except for individuals qualified in radiation protection procedures. or -

personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry-personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas. >

4 9

4 0

o 2/14/98 Revision D a

F f'

JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 SECTION 5.0 ADMINISTRATIVE CONTROLS GENERIC CHANGES (C)

C3 This change is consistent with NUREG-1431, as modified by TSTF-65.

Consistent with the philosophy of TSTF-65. 5.2.1.c bracketed information states a corporate officer. The plant specific title for the person holding these responsibilities will be delineated in the 0A Program.

The modifications to Specification 5.7 proposed in TSTF-65 were not incorporated based on CTS alant specific information. In addition, the l plant specific title of "Slift Manager" is retained.

C, This change is consistent with NUREG-1431. as modified by WOG-56. NUREG Specification 5.2.2.b has been deleted. This Section contains information that is duplicative of 10 CFR 50.54(m)(2)(iii) requirements .

and is not required in the TS to ensure the public health and safety.

C3 Not used.

C. These changes are consistent with NUREG-1431. as modified by TSTF-152.

C3 This change is consistent with NUREG-1431. as modified by TSTF-52. The acceptance criteria of 5.5.16.a is modified to delete the " equals to."

portion of 5 0.60 L and s 0.75 L . For consistency with Appendix J.

minor editorial cor,rection to tha't proposed in TSTF-52 have been made.

O T plant specific requested exception to NEI 94-01 is added.

C6 This change is consistent with NUREG-1431. as modified by TSTF-115.

Minor editorial format corrections have been made (1. 2.. have been changed to a. . b. , . . ) consistent with other Specification 5.0 programs.

C7 This change is consistent with NUREG-1431. as modified by an editorial change provided to the NRC.

C, This change is consistent with NUREG-1431. as modified by WOG-72. This change revises 5.5.4.e wording to describe the actual. intent of the dose projections. GL 89-01 provides the wording which basically combine the 2 requirements for cumulative and projected dose. This can be read to require a plant to make projected doses for the quarter and year every 31 days. It is only necessary and reasonable to make a projection for the next 31 days (and not to project the quarter and yearly dose). A cumulative dose projection would still be done for the current calendar quarter and year per the ODCM. The new proposed words are the same as pre-GL 89-01 implementation.

Og TSTF-4 Revision 1. proposed revisions to the PTLR definition. However, the' change did not include similar revisions to Section 5.0. For consistency the PTLR description is revised to add the PORV lift settings.

N BYRON /BRAIDWOOD UNITS 1 & 2 5.0 2 2/14/98 Revision D

p JUSTIFICATION FOR DIFFERENCES TO NUREG 1431

/ SECTION 5.0 ADMINISTRATIVE CONTROLS PLANT SPECIFIC CHANGES (P)

P; During the development certain wording preferences. English language conventions, reformatting, renumbering. or editorial rewording consistent with plant specific nomenclature were adopted. As a result, the Technical Specifications (TS) should be more readily readable by, and therefore understandable to. plant operators and other users.

During this reformatting, renumbering, and rewording process, no ,

technical changes (either actual or interpretational) were made to the TS unless they were identified and justified.

P, ITS Specifications 5.1. 5.2. and 5.3 were revised to retain plant specific wording preferences. The second paragraph of ..

Specification 5.1.1. regarding review and approval of tests or experiments is deleted. CTS do not delineate this requirement.

Specification 5.1.2 is revised to reflect plant practice. The Shift l Manager is responsible for directing the control room command function but is not necessarily in the control room. An SR0 is in the control room and has the control room command function, when either unit is in MODE 1. 2. 3. or 4. With a common control room su] porting two unit operation, the practice is to have an individual SR0 responsible for the control room command function for g.adl unit. Specification 5.2.2.a is modified to clearly delineate CTS requirements for non-licensed O operators.

P3 ITS Specifications 5.5.4.b and 5.5.4.g are revised to retain plant specific wording preferences reflect CTS requirements. These changes are in accordance with changes approved in an SER dated December 30, 1993.

P. ITS Specifications 5.5.6. 5.5.7. and 5.5.11 are revised to clarify general conformance to the applicable Regulatory Guides. This change is necessary since the UFSAR contains plant specific exceptions to these Regulatory Guides. Thi.s eliminates the potential for misinterpretation of the licensing basis requirements. This is an editorial enhancement only and does not involve a technical change.

P,' ITS Specification 5.6.2 was revised to delete specific details of the annual radiological environmental operating report. This change is in '

accordance with changes approved in an SER dated April 13. 1992.

P. Byron and Braidwood utilize blended ASTM #1 and #2 fuel oil. Therefore references to #2 fuel oil in NUREG 5.5.13 are deleted. )

BYRON /BRAIDWOOD UNITS 1 & 2 5.0 3 2/14/98 Revision D l

1

i:

JUSTIFICATION FOR DIFFERENCES TO NUREG 1431 SECTION 5.0 - ADMINISTRATIVE CONTROLS Pu NUREG Specification 5.5.14 is modified to add the allowance to provide the NRC Bases updates on a frequency consistent with any exemptions to 10 CFR 50.71(e), the utility has received. This change is consistent with the wording in ITS Specification 5.5.16.

Pu The NUREG Specification 5.6.7 reference to ITS LC0 3.3.3 Conditions is modified consistent with the plant specific development of ITS LCO 3.3.3.

P3 NUREG Specification 5.5.3 " Post Accident Sampling," is revised consistent with CTS. to state " radioactive iodines and particulates in plant gaseous...," rather than NUREG wording of radioactive gases, and particulates in plant. ." The NUREG words imply a more stringent ,

requirement than CTS.

Pa Consistent with CTS 4.8.1.1.2.d.2), the sampling time frame specified in 5.5.13.b is revised to 30 days.

Pn ITS Specification 5.6.6.c.2 provides a reference to the plant specific PTLR. This report will be 3rovided for NRC review and approval to

. support final approval of t7e ITS.

P, ITS Specification 5.5.6. " Pre-Stressed Concrete Containment Tendon O

3 Surveillance Program." was revised to conform to Comed's commitment to comply with 10 CFR 50.55a. the ASME Boiler and Pressure Vessel Code 1992 Addenda, and Regulatory Guide 1.35.1 dated July 1990. In addition. ITS 5.6.8. " Tendon Surveillance Report." was revised to be consistent with .

the proposed changes to ITS Specification 5.5.6.

P,2 These changes are being made based on discussions with the NRC reviewer, and Comed Byron and Braidwood ITS Project Groups and Health Physics Departments.

I

( . BYRON /BRAIDWOOD UNITS 1 & 2 5.0 5 2/14/98 Revision D