ML20207L520

Summary of 880412 Meeting W/Util in Rockville,Md Re Planned Changes to Tech Spec 6.0 Concerning Administrative Controls, Tech Spec Development & Review Schedule & NRC Review of Proposed Tech Spec Changes

ML20207L520
Person / Time
Site:	Comanche Peak
Issue date:	10/04/1988
From:	Malloy M NRC OFFICE OF SPECIAL PROJECTS
To:	NRC OFFICE OF SPECIAL PROJECTS
References
NUDOCS 8810170334
Download: ML20207L520 (59)

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.....# OCT 4 P^oo Cocket No. 50-445 APPLICANT: Texas Utilities Electric Company (TV Electric)

FACILITY: Comanche Peak Steam Electric Station (CPSES), Unit 1 SUEJECT: $JMMARY OF MEETlf.G ON APRIL 12, 1958 - CPSES UNIT 1 TECHNICAL SPECIFICATICNS Cn April 12, 1988 NRC staff and representatives of TV Electric, lead applicant for the CPSES, ret in Rockville, Marylend to discuss (1) TV Electric's planned changes to Section 6.0 (Administrative Controls) of the Unit 1 Technical Spec'fications (TS), (2) the Ui'it 1 TS development and review schedule, and (3) hRC review of proposed Unit 1 TS changes which the staff has identified as "generic."' The meetirg notice and list of attendees are provided as Enclosures 1 and 2, respectively, to this surrrnary.

TS Schedule As backgrcund, on March 2, 1968, in forwarcing the second draft version of the Unit 1 TS for TV Electric's review, the staff requested the applicant to reconsider the June 30, 1988 date previously indicated as the date it anticipated NRC issuance of the TS as Appervix A to the Unit 1 operating license. Based on a schecule reevaluation conducted in March 1968 TV Electric announced a change in the scheculed date for Unit I fuel loading from August 1988 to June 1, 1989. In view of this announterent, in a letter dated March 25, 1983 (TXX-68345), TV Electric requested NRC issuance of the "Proof and Review" sersten of the Unit 1 TS by Cecerter 30, 19Eb in anticipation of issuance of the final TS on June 1, 1989.

In view of the applicant's schetivle changes, at this meeting the staf f expressec its desire to firm up it: review schedule before the end of April 1988. The staff and applicant examined the staff's basic TS review schedule anc ciscussed the timing proposed in TV Electric's March 25, 1965 letter. The staff pointed cut its need to maintain the CPSES TS review within the tive constraints of the basic schedule in order to centrol th9 staff's workload anc resources. The staff inferred TV Electric that if it needed the "Proof and Revie." version by Decenter 30, 1955, the basic schedule would dictate completion of the TS 1r. April 1969, nearly 2 months before scheduled Unit I fuel load. Crice the final TS are issv6d, the staff saic it would not

• These are cher.ges which appear to te applicable to any 4 loop nestinPtuse cressuritec wJter reacter eN O nct cppear to te Ccc ancne Peak plant-specific.

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1 4 TV Electric nrr 3 gg entertain additional changes prior to fuel loading unless there was a safety problem that dictated a TS change. TV Electric agreed to reassess their needs )

and get back with the staff within a week so the staff can solidify the Unit 1 l TS schedule. l Staff Review of Generic Changes to the Unit 1 TS  !

l TV Electric provided un overview of their new TS programs. The 5 presentation slides used during thic discussion are provided as Enclosure 3.

Following this introduction, TV Electric directed the discussions towards proposed changes to the Unit 1 TS which vary from the Standard Technical l Specifications (STS) and which the staff has previously indicated must be l reviewed by the staff as generic changes. Mr. Emch, Section Chief in OTSB, l explained how the staff determines whether a proposed change is generic and what is required of the staff in the way of the review (documentetion and I resources). He also discussed the hRC Interim Policy Statement on TS i Improvements (52 FR 3788, February 6, 1987) anu 6e efforts and schedules of  ;

the staff and the Westinghouse Owners Group to p' , duce revised STS. While work continues on the NRC TS Improvement Program, Mr. Emch advised TV Electric that the staff can handle only a certain number of the many generic changes TV Electric has proposed. The staff indicated that it needs to know the i relative importance of these changes so it has some basis to determine which I ones it has the resoure.es to review. The applicant suggested that review of j their many changes migne not be as resource-intensive as the staff expects. 1 TV Electric pointed out that in many cases, one or more plants already have l an identical or similar change incorporated in their TS. The applicant l prooosed that the TS items could be added to the review materials for the  !

various NRC branches which will be performing general FSAR review for Comanche i Peak. l TV Electric indicated that it needed to decide how it wanted to proceed further on this issue. The staff will consider how many generic TS changes it l can support. The applicant provided a copy of their current "Sumary of Outstanding Technical Specifications Issues" which is included as Enclosure 4 to this summary.

Planneo Change to TS Section 6.0 The remainder of the meeting was devoted to discussions of changes planned by TU Electric for the Administrative Controls section of the Unit 1 TS. TV Electric started with a brief overview of its operations organization. The 4 presentation slides used in this overview are provided as Enclosure 5.

The applicant provided for discussion a markup of Section 6.0 of the second draft TS with change bars ano numbers in the margin which correspond to a listirg of the changes and their proposed Justification. This handout is j provided as Enclosure 6. The staff and applicant discussed each of these ,

changes in turn, with Mr. Allenspach, the staff reviewer from LPES, providing l preliuinary coments on the changes.  ;

1 I

_ ,_ __- _ _ _ . _ _ .__ _ _ _ _ ._ _____.__ i

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Conclusion following a brief staff caucus, the following actions were sunmarized:

1. TU Electric will caucus on the TS schedule and advise the scaff. l

2. TV Electric will caucus on the issue of generic TS ch6nges and advise the <

staff on how it wishes to proceed. f i

3. The staff will consider the subject of generic TS changes and how many it i can support.

In addition, the staff requested the applicant to provide an annotated summary of plant specific vs. generic TS changes, as indicated by NRC curing the TS i meeting held during the week of January 11, 1988. The categories to be noted are: plant-specific, generic-deletion, generic-addition, and generic-correction, j d .f Y $L '

Melinda Malloy, Project ager Comanche Peak Project 01 sion  !

Office of Special Projects

Enclosures:

1. Meetir.g Notice 1

2. List of Attendees  !

3. TV Electric TS Programs Presentation Slides 4 TV Electric's Summary of Outstanding TS Issues

5. TV Electric Operating Organization Presentation Slides

6. Planned Changes to Section 6.0 of Unit 1 TS cc w/ enclosures:

See next page I

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. l W. G. Counsil Comanche Peak Steam Electric Station 2

Texas Utilities Electric Company Units 1 and 2

. cc:

l Jack R. Newman, Esq. Asst. Director for Inspec. Programs Newman & Holtzinger, P.C. Comanche Peak Project Division Suite 1000 U.S. fluclear Regulatory Conunission '

1615 L Street, N.W. P. O. Box 1029 Washington, D.C. 20030 Granbury, Texas 76048 ,

Robert A. Wooldridge, Esq. Regional Administrator, Region IV

Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011

Dallu, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Director of Nuclear Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C. 20002 ,

Skyway Tower 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde, Esq.

Dallas, Texas 75201 Government Accountability Project ,

Midwest Office

, Mr. R. W. Ackley 104 East Wisconsin Avenue .

Stone & Webster Appleton, Wisconsin 54911 t Comanche Peak Steam Electric Station P. O. Box 1002 David R. Pigott, Esq.

Glen Rose Texas 76043 Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. J. L. Vota San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.

I Pittsburgh, Pennsylvania 15230 Suite 600 a

1401 New York Avenue, NW Susan M. Theisen Washington, D.C. 20005 .

Assistant Attorney General

Environmental Protection Division Robert Jablon L

P. O. Box 12548, Capitol Station Bonnie S. Blair  ;

! Austin, Texas 78711-1548 Spiegel & McDiarmid  !

1 1350 New York Avenue, NW j Mrs. Juanita Ellis, President Washington, D.C. 20005-4798

Citi

ens Association for Sound Energy i 1426 South Polk George A. Parker, Chairtaan

Dallas, Texas 75224 Fublic utility Conrnittee 4 Senior Citizens Alliance Of .

Ms. Nancy H. Williams Tarrant County, Inc.

1 CYGNA Energy Services 6048 Wonder Drive I 2121 N. California Elvd., Suite 390 Fort Worth, Texas 76133 j l Walnut Creek, CA 94596 l i

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. . OCT 4 1938 W. G. Counsil Comanche Peak Electric Station Texas Utilities Electric Company Units 1 and 2

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Joseph F. Fulbright Fulbright & Jaworski 1301 McA1nney Street ,

Houston, lexas 77010 1 Roger D. Walker Manager, Nuclear Licensing l Texas Utilities Electric Company Skyway Tower 400 North Olive Street, L.B. 81 4

Dallas, Texas 75201 Texas Utilities Electric Company i c/o Bethesda Licensing l 4 3 Metro Center, Suite 610 )

Bethesda, Maryland 20814 William A. Burchette, Esq. i Counsel for Tex-La Electric Cooperative l I

of Texas Heron, Burchette, Ruckert & Rothwell Suite 700 '

1025 Thomas Jefferson Street, NW Washington, D.C. 20007 GDS ASSOCIATES, INC. j Suite 720 1850 Parkway Place i Marietta, Georgia 30067-8237 l

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. UNITED STATES

.3.c q NUCLE AR REGULATORY COMMISSION j

W A SHING TON. D. C. 20$55

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_f l Decket No. 50-445 MEMORANDUM FOR: Christopher I. Grimes, Director  !

Comanche Peak Project Division '

l Office of Spt.cial Projects f' l THRU: James H. Wilson, Assistant Direct 0 [ g%#t for Projects / l Comanche Peak Project Division Office of Special Projects @ O /M; /k ,

FROM: Melinda Malloy, Project Manager Comanche Peak Project Division Office of Special Projects

SUBJECT:

FORTHCCMING MEETING WITH TU ELECTRIC Date & Time:  :, '.:::

Tuesday, f; "@'l00 A 51>\ ghff/f/%/

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Location: One White Flint North g 11555 Rockvill Pike '

Room ':0 ' / O/3 M uwA, ~

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Rockville, MD 20852 '

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Purpose:

For Applicant to discuss proposed chan es to Technical Specifications for Comanche eak 30 Q Steam Electric Station, Unit 1 Participants *: NRC Applicant F Malloy R. Walker, et al.

R. Giardina E. McKenna F. Allenspach ' <

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Melinda Malloy, Project /Ma ager Comanche Peak Project Di sion Office of Special Projects cc: See next page CONTACTS: Melinda Malloy er James H. Wilson (301)a92-0738 (301)492-3306

• Heetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant tc "Open Meetints and Statement of hRC Staff Policy," Federal Register 28058, 6/28/78.

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W. G. Counsil Comanche Peak Steam Electric Station Texas utilities Electric Company Units 1 and 2 cc:

Jack R. Newman, Esq. Asst. Director for Inspec. Programs Newman & Holtzinger, P.C. Comanche Peak Project Division Suite 1000 U.S. Nuclear Regulatory Commission 1615 L Street, N.W. P. O. Box 1029 '

Washington. 0.C. 20036 Granbury, Texas 76048 Robert A. Wooldridge, Esq. Regional Administrator, Region IV Worsham, Forsythe, Sampels & U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive, Suite 1000 2001 Bryan Tower, Suite 2500 Arlington, Texas 76011 Dallas, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Director of Nuclear Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C. 20002 Skyway Tower 400 North Olive Street, L.B. 81 Ms. Billie Pirner Garde. Esq.

Dallas, Texas 75201 Government Accountability Project Midwest Office Mr. Robert E. Ballard, Jr. 104 East Wisconsin Avenue Director of Projects Appleton, Wisconsin 54911 Gibbs and Hill, Inc.

11 Penn Plaza New York, New York 10001 David R. Pigott, Esq.

Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. R. S. Howard San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.  ;

Pittsburgh, Pennsylvania 15230 Suite 600  !

1401 New York Avenue, NW Renea Hicks Esq. Washington, D.C. 20005 Assistant Attorney General Environmental Protection Division Robert Jablon P. O. Box 12548, Capitol Station Bonnie S. Blair Austin, Texas 78711 Spiegel & McDiarmid 1350 New York Avenue, hW Mrs. Juanita Ellis, President Washington. 0.C. 20005 4798 Citizens Association for Sound Energy George A. Parker, Chairman  ;

1426 South Polk Dallas, Texas 75224 Public Utility Comittee Senior Citizens Alliance Of Ms. Nancy H. Williams Tarrant County, Inc.

CYGNA Energy Services 6046 Wonder Drive 2121 N. California Blvo., Suite 390 Fort Worth, Texas 76133 Walnut CrNk, CA 94596 .

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Comanche Peak Electric Station <

W. G. Counsil Units 1 and 2 Texas Utilities Electric Company 1

cc: ,

Joseph F. Fulbright '

Fulbright & Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager, Nuclear Licensing Texas Utilities Electric Comoany .

Skyway Tower ,

400 North Olive Street, L.B. 81 Dallas, Texas 75201 Mr. Jack Redding  !

c/o Bethesda Licensing Texas Utilities Electric Company -

3 Metro Center, Suite 610 l Bethesda, Maryland 20814 William A. Burchette. Esq.

Counsel for Tex-La Electric Cooperative of Texas Her9n, Burchette, Ruckert & Rothwell l Suite 700 1025 Thomas Jefferson Street NW Washington. 0.C. 20007 GOS ASSOCIATES, INC.  ;

Suite 720 '

1850 Parkway Place Marietta, Georgia 30067-8237 Aoministrative Judge Peter Bloch U.S. Nuclear Regulatory Comission Washington. 0.C. 20555 Elizabeth 8. Johnson Acniinistrative Judge Oak Ridge National Laboratory ,

P. 0. Box X. Building 3500  !

Oak Ridge, Tennessee 37830 Dr. Kenneth A. McColicm I 1107 West Xnapp l Stillwater, Oklahoira 74075 Dr. Walter H. Jordan 881 West Outer Drive Oak Rioge, TN 37830 l

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. Enclosure 2 kRC/TV ELECTRIC NEETING ON TECHNICAL SPECIFICATIONS '

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APRIL 5, 1988 ATTENDEES Name Affiliation d m.c s. J tle.I(e, 3s T 4 E teu tri t l ffa.y , P LQ Jh;c. ru FF c ~i' '

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- TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM (TSIP) 1

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Criteria and references used as guidance for developing the TSIP j

NRC's Interim Policy Statement (52FR3788), February 6,1987 l

l - Westinghouse Owners Group MERITS Program

- CPSES Management Guidance

• Technical Specifications requested for relocation to the TSIP

• Administrative control of revisions .

1 i

l l

TURBINE OVERSPEED PROTECTION RELIAB!LITY PROGRAM (TOPRP) i j Criteria and references used as guidance for developing the TOPRP l - Callaway's Turbine Overspeed Protection Reliability Program (Approved by the NRC)

- Steam Turbine-Generator Instruction Manual i

• General description of progrant i

l

• Administrative control of revisions -

i i

~

l 1

RADIOACTIVE EFFLUENT and ENVIRONMENTAL MONITORING MANUAL l (REEMM) i Criteria and references used as guidance for developing the REEMM I -

Radioactive Effluent Monitoring Manual submitted by NEU Millstone Unit 3 (Approved by the NRC) 4

) -

NRC's Interim Policy Statement (52FR3788), February 6,1987 i - Westinghouse Owners Group MERITS Program

- CPSES Management Guidance

!

• Technical Specifications requested for relocation to the REEMM c

• Administrative control of revisions i

I i

I FIRE PROTECTION PROGRAh!

~

4 (FPP) 4

• Criteria and references used as a guideline for developing FPP

! - Perry's Fire Protection Program ( Approved by the NRC) l 1 - Generic Letter 86-10 (4/24/86)

- General description of program l

• Administrative control of revisions ,

l. - - _ - - - - - - - - _ _ - _ _ - _ - . _ _ _ - _ _ _ _ _ - - _ - - _

~

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Enclosure i

SUMMARY

OF OUTSTANDING TECHNICAL SPECIFICATION ISSUE 9 _

TSIP - Technical Specification Irnprovement Prograrn L

t REEMM - Radioactiva Effluent and Envirentnental Monitorirg Manual i

Item No. T S. No. Title Surnmarv of Chantle i

1. 2.2.1 RTS Instrurnent Setpoint Make the P-10 setpoint a ,

norninal value (10%).

2. 3.1.3.1 Movable Control Rods Change Action Staternents to Group Height cover the situation of rnore than one rod trippable but inoperable. l

3. 3.1.3.3 Position Indication Add note to allow Operability j Syst ern testing after rnaintenance.

4. 3.2.3 Hot Channel Factor Move the requirernents for RCS and and flow verification frorn Hot 3.2.5 DNB Parameters Channel Factor to the DNB 1 Pararneters Specificat ion.

Add Special Test exception to i

provide for startup testing.

5. 3.2.4 Quadrant Power Ti'.t Sirnpli fy the Act ion Stat ernent Ratio for increased usability.

6. 3.3.1 RTS Inst rurnent at ion Split SRNI spec. for reactor trip breakers open or shut and change Action Staternents.

Add requirernent for Reactor Trip Bypass Breaker Testing.

(Will require review of i

WCAP-11312.)

\

Change powde litnit frorn 75% to j

50% as to when an incore-excore  !

calibration for axial flux l difference.

Relocate RTS response t irne to j the TSIP.

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1 Etem No. T. S. No. Title Summary of Charg j

7. 3.3.2 Engineering Safety Rernove auxiliary feedwater Features manual initiation requirement. l i

Remove Trip of All Main Feed i Purno requirernent. i Change Loss of Power to rernove component level listing and  ;

include alternate off-site  !

power testing. i Relocate ESFAs response tirnos to the TSIP.

t t 8. 3.3.3.1 Radiation Monitoring Remove Particulate Radiation signal for Cont aintnent l Ventilation Isolation (CVI).

1 Rernove Criticality Monitors for fuel storage areas.

i Change applicability for CVI i

requirement.

9. 3.3.3.2 Moveable Incore Relocate entire Specification Detectors to the TSIP.

10. 3.3.3.3 Seismic Inst rutnent at ion Change allowed time to perforrn channel calibration.

11. 3.3.3.4 Meteorological Relocate entire Specification Instrumentation to the TSIP.

13. 3.3.3.6 Accident Monitoring Change instruments to only encornoass Type "A" i nst rurnent s.

13. 3.3.3.9 Loose Parts Detaction Relocate ontire Spectfication l l to the TSIP. '

! 14, 3.3.3.11 Radioactive Gaseous Change note for hydrogen and j Effluent Monitor oxygen channel calibration to use rnanufactures recommended 4

test gas.

15. 3.3.4 Turbine Overspeed Relocate to the Turbine

.; Reliability Oversceed Protection Re11 ability Prograrn.

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1 It ern No. T. S. No. Title Summary of Chance

16. 3.4.2 RCS Safety Valves Remove requirement to nave Safety Valves when in Modes 4, 5 and 6.

17. 3.4.4 RCS Relief Valves Change Action Staternents to apply within the applicability.

l 18. 3.4.5 Stearn Generators Relocate entire Specification l

l to the TSIP.

l 19. 3.4.6.2 Operational Leakage Add allowance for reduced i

pressure testing.

I i Change the check on usal flow l

to agree with the way ECCS systern is checked.

Change tn inventory balance to allow for plant start up, l

! 20. 3.4.9.1 Dressure Ternperat ure Relocate the reactor vessel L irni t s rnat ori al irradiation surveillance to the TSIP.

21. 3. 4. 3. 2 Pressuri:er Rernove rnaxirnum auxiliary soray l di f f erent ial t eroperat ure lirait.

l l 22, 3.4.9.3 Overoressure Protection Add RHR relief valves as a l System possible overpress protection relief path.

23, 3. 5.1 Accurnulators Add new Action Statement to address boron concentration out ,

l of specification. l Retnove the Analog Channel Operat ional Test requirernent.

24, 3.6.1.1 Containment Integetty Add exclusion for verificat ion of the blind flange en the fuel transfer canal exesnt once after draina08 of the Canal.

25. 3.6.1.3 Cont a i ntnent Airlocks Add allowance to ocin the one Operable airlock for roa i nt enance.

3

Item No. T. S. No. T_11[g Surornary of Chance 26, 3.6.1.4 Internal Pressure Change Action tirne lirait f r ern i nour to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

27. 3. 6.1. 5 Cont a intnent Air Changed for new system design.

Ternperat ure

28. 3.6.1.7 Containment Ventilation Change allows for the pressure Syst ern relief valve to be as necessary  ;

for pressure reduction with no t irne restrict ions.

29. 3.6.3 Cont aintnant Isolation Relocate containtnent isolation l Valved valve table to the TSIP.

Rernovo requirernent to test during Cold Shutdown or refueling Modes.

(

30. 3.7.1.2 Auxiliary Feedwater Change surveillance frequency 1

from 31 days to 92 days.

31. 3. 7.1. 5 Main Steam Isolation Add allowance for post Valves rnaintenance testing in Modes 2 l and 3.

32. 3.7.5 Ultitaate Heat Sink Change the requirement to evaluate the situation vice i requiring dredging when the sed irnent level reaches 1.5 feet.

J3. 3.7.7 Control Roorn HVAC Change to agree with the ANSI j Standard and Regulatory Guide as corarnitted to in the FSAR.

34. 3.7.8 Prirnary Plant Change to agree with the ANSI l Ventilation Standard and Regulatory Guide as cerimitted to in the FSAR.

35. 3.7.9 Snubbers Relocate entire Specification to the TSIP.

36. 3.7.10 Sealed Source Change to allow testing of Cont arni nat t on fission detectors prior to installation.

Relocate entire Specification to the TSIP.

4

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I ftem j No. T. S. No. Title Summary of Chance

37. 3.7.13 Area Ternperature This soecification changed to

Monitoring incorporate new equiprnent

! quali ficat ion infortnat ion.

a

! 38. 3.8.1.1 A. C. Sources - Change Action Staternents to

] Operating address Generic Letter 84-15.

a Change to minimize to cold

starts on the diesel generators (DG).

J Remove loading of the DG t iram requirements.

Expand on what is the largest load to be rejected.

Add allowances for grid disturbances.

I Remove testing of rnechanical interlocks.

Rernove reborting and requalification requirements.

, 39. 3. 8.1. 2 A. C. Sources - Modify the depressurizatien Shutdown recei rernent in the Action j

{ Statement to reference the '

Overpressure Protection Systern l Specification.

l

} 40. 3. 8. 3. 2 Onsite Power Dist. -

Modify the depressurization '

Shutdown requirement in the Action  !

St at ernant to reference the (

i Overoressure Protection System ,

Specification. '

! 41. 3. A. 4.1 A. C. Circuits Inside Rernove this Specification. i l Cont a i ntnent

42. 3.8.4.2 Overetreent Protective Relocate table of protective Devices devices to the TSIP. {

1 i l Change test ing requirernent to a

allow use of the rnanufacturers i

! provided data.

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{ i j No. T. S. No. TM Summary of Chance {

43. 3.9.11 Fuel Storage Air Remove this specification.

l Cleanum System 1

44, 3.10.2 Group Height and Power Add Soecification 3.2.3 (power l Distribution distribution) to this '

Specification.

, 45. 3.11:1.1 Liquid Effluents Relocate the Liquid Effluent l

) Table to the REEMM. l l i

46. 3.11.1.3 Liouid Radwaste Relocate entire Specification l

Treatment to the REEMM.  ;

i

47. 3.11.1.4 Liquid Holdup Tanks Relocate entire Specification 4

to the REEMM.  !

t

.: 48. 3.11.2.1 Gaseous Effluent Add 3.0.3 exception j

(Deze Rate) r 1  :

Relocate the Gaseous. Effluent  !

Table to the REEMM.  !

49. 3.11.2.4 Gaseous Radwaste Relocate entire Specification Treatment to the REEMM.

50. 3.11.2.5 Exolosive Gas (11xture Remove requirement to j continuously monitor.

51. 3.11.2.6 Gas Storage Tanks Relocate entire Specificatior to the REEMM. '

1

' I Change sample frequency frore 24 ;

1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 92 days.

52. 3.11.3 Solid Rad Waste Relocate entire Specification l to the REEMM.

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53. 3.11.4 Total Dose Relocate entire Soecification to the REEMM.

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54. 3.12 Radiological Env. Relocate entire Radiological Monitoring Environment Monitoring

^ Technical Specification to the i

REEMM.

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. o Enclosurc 6 JUST!FICATIONS SECTION 6.0 j

- All page numbers reflect the secona draft page numbers.

- All change bars without number identifers are editorial changes Change # Dage #

1. 6-1 These changes remove the requirement to maintain 6-2 an organizational chart in the Toch Specs. The 6-3 information that is being removed from the Tech 6-4 Specs is contained in the FSAR and updated in

, accordance with 10CFR50.71. This change is made in conformance with Generic Letter 88-06. l

2. 6-4 This change adds the ability tc allow for personnel to be task qualified. This is based on l

. the fact that training can be accomplished on a  !

, specific task that does not require an overall indepth knowledge of a position as defined in ANSI-N18.1-1971. This allows for a person to be 2

used as a working member of the staff after completing task qualification and continue to work towards position qualification. This change is similar to that licensed at Vogtle.

3. 6-7 This change identifies the SORC composition for CPSES. This change is made for two baste reasons.

The first reason is to eliminate the possibility of having to make a Tech Spec change due to a management reorganization that eliminates, adds, combines or Just renames organizational positions.

The second reason is to allow the flexibility for the Vice President, Nuclear Operation to designate the most qualified personnel to represent the required areas on SORC. This will result in a i higher technical level of competence and i maximizing consistency, i 4 6-7 The appointment of alternates is stated in the previous section.

5. 6-7 This note is for, and included on the previous  !

page, therefore should be deleted. l

6. 6-8 Change the quorum requirement to 5 members and the chateman vice 4 members and the chairman. This is I base on having the majority of the SORC areas j represented in every SORC meeting.  !

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l Change 4 Page #

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! 7. 6-8 Change the woroing to ensure that there is no confusion as to which administration procedures i

have to be reviewed by SORC. This is cased on the

! SORC will review all procedures contained in the l

Station Administration Manual. Those are procedures which disseminate to all departments

, within Nuclear Operations how business will be conducted and guidance in writing interdepartmental procedures.  ;

l i

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8. 6-8 This change deletes the word "may" since this 5 makes the review performed by SORC on specific l situations described in the Tech Specs. With the  !

word "may" included it would require that SORC  !

review all proposed procedures, changes to procedures, equipment, systems, facilities, proposed tests or experiments. This would be so  :

time consuming that it would significantly detract j from the real responsibility of SORC to be i cognizant of actual safety concerns.

l

9. 6-9 Add review of changes to the Radioactive Effluent and Environmental Monitoring Manual (REEMM) to l SORC responsibilities. This is based on, the requirements of Specification 3/4.11 (inpart) and 3/4.12 are being relocated to the REEMM for '

implementation and control. This requirement is an extension of the new Specification 6.15.

)

10. 6-9 Added a new requirement for SORC to review the Technical Specification Improvement Program (TS!P) and several editorial corrections as a result.

This is based on the requirements of several Specifications and parts of Specifications are being relocated to the TSIA for implementation and control. This ensures that any changes made to the TSID receive the highest level of review consistent with other documents of the same importance.

11. 6-9 Change so that SORC makes recommendations to the designated approval authority as defined in 6.5.3.

This is explicitly required since the Vice President, Nuclear Operations has deligated the j i

approval authority for departmental peccedures to I the responsible department manager. Item 6.5.1.6b which controls the review of safety evaluations on gli procedures, SORC will be making recommendations to the responsible department ,

manager for approval or disapproval. l l

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i 12. 6-3 Deleted the requirement for SORC to recommend in

, writing approval or disapproval of 6.5.1.6i i

! through 6.5.1.61. This is based on L v Standard Technical Specifications only require that i l

j responsibilities from 6.5.1.6a through 6.5.1.6e l l have this specific requirement. Each item (1) through (k) have separate requirements, 6.13 through 6.16, and (1) already specifies where to l forward the required reports.

I

13. 6-12 Added the requirements to perform an audit of the l I

Radioactive Effluent and Environmental Monitoring l Manual (REEMM). The REEMM incorporates the l

! Radiological Environmental Monitoring Program, 1 i therefces due to the increase in the material to ,

) be audite1 the frequency has been increased to 24 j months, this also makes it consistent with the (

ODCM. This change is similar to that licensed at i Millstone 3.

q 14. 6-12 Added the requirement to perform an audit of the i j Technical Specification Improvement Program l J (TS!P). This is to ensure that all requirements j i located to the TS!P are implemented in a correct '

• • manner.

j I

i 15. 6-14 Changed the approval authority for 2haiget to the j Security Plan and Emergency Plan, as well as changes to the implementing procedures, to the j Vice President, Nuclear Operations. This is consistent with Specification 6.5.3.1a.

l 16. 6-15 Added the Station Operations Review Committee for j distribution of License Event Reports and made minor editorial changes to more closely agree with j the standard technical specifications.

J l 17. 6-15 Added to the list of Procedures and procrams are j the Radioactive Effluent and Environmental Monitoring Manual, Fire Protection Program and 1 Technical Specification Improvement Program. This

] will ensure procedures are written to implemen?

these programs and changes to these procedures are reviewed per Specification 6.5.

18. 6-15 Replace these sections with a section which 3 references the previous Specification 6.5.

1 Specification 6.5 has the same recuirement as the j replaced section with the exception that all the 1 procedures of Specification 6.8.1 are not approved

) by the Vice President, Nuclear Operations as i 1

discussed for Specification 6.5.3.1. l

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l Change # Page #

19. 6-17 Addec the description of the Radioactive Effluent and Environmental Monitoring Manual to provide i basic guidance, controls and limitations for '

sampling and analysis for requirements of the Technical Specifications that are being relocated  ;

to the Radioactive Effluent and Environmental ,

Monitoring Manual. This change is s1*nitar to that licensed at Millstone 3.

20. 6-19 The reporting requirements are being maintained j 6-20 with in the Technical Specification for the Annual 6-21 Radiological Environmental Operating Report and 6-22 the Semiannual Radioactive Effluent Release Report. The specific details of what information must be included in these reports is being relocated to the Radioactive Effluent and i Environmental Monitoring Manual. This change is nimilar to that licensed at Millstone 3.

21. 5-22 The note requiring the use of specific WCAPs for

the analytical methods used to generate the Fsub(xy) limit has been deleted. The sentence is very specific in the fact that whatever method is useo, it must be previously reviewed and approved by,the NRC. This enange may prevent an unnecessary change in the future.

22. 6-23 Added the Technical Specification Improvement Program and Radioactive Effluent and Environmental Monitoring Manual to ensure that the records l produced from the implementation of these I documents are retained for a finite period of time. {

l

23. 6-24 Clarified the requirement to retain quality l assurance activities that are required to be retained for the life of the plant by the Quality

, Assurance Manual. This is to prevent the confusion that ggy activities required by the Quality Assurance Manual have to be retained for j the life of the plant, which is not the intent.

24 6-25 Changs the reference from the snubber Technical i Specification to the Technical SDecification Improvement Program. This is based on the snubber

requirements being shifted to ASME Section XI and

will be implemented through the Technical l Specification In.orovement Program.

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Change e Page #

25, 6-26 Add a new section to set the adrainistrative i controls under which the Radioactive Effluent and i

Environenental Monitoring Manual is initially i

! aporoved and how all changes initlated by the l Licwnsee are reviewed and approved.  :

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SECTION 6.0 ADMINISTRATIVE CONTROLS l

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. . ACM!N!$7RAffvE CONTROLS ,

G .1 RESPONS!8!LITY 5.1.1 The Vice President, Nuclear Operations shall be responsible for overell operation of the site, while the Manager, Plant Operations shall be responsiole for operation of the unit. The Vice President, Nuclear Operations and Manager, Plant Operations shall each delegate in writing the succession to this respon-sibility during their absence.

6.1.2 The Shift Supervisor (or during his absence frem the control room, a designated individual) shall be responsible for the control room commano function. A management directive to this effect, signed by the Vice President, Nuclear Operations snall be reissued to all station personnel on an annual casts.

6.2 ORGANIZATICN .

OFFS!TE

. . .. . ..f .ij 5 5 )5 55.5 . i. 52..

,g .4 UNIT STAFF i

n 6.2.2 The unit organization shall be ;;Qest C;ur 'ta th';felle

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a. Each on-duty shift shall be composed of at least the minimum shift  !

crew composition shown in Table 6.2-1; l

b. At least one licensed Operator shall be in the control room wnen fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4 at least one itcensed Senior Ocerator shall be in the control room;

c. A Radiation Protection Technician

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

)

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

e. A site Fire Brigade of at least five memcers" shall be maintained on I site at all ti.ses. The Fire Brigade shall not include the Shift l l Supervisor and the two other someers of the minimum shif t crew necessary for safe shutdown of the unit and any personnel required l for other essential functions during a fire emergency; and '

i i

"The Radiation Protection Technician and Fire Brigace composition may be less than the minimum requirements for a period of time not to exceed 2 nours in order to accomodate unexpected absence, provided imediate action is taten to fill the require; positions.

CCMANCHE PEAA - UNIT 1 6-1 '

. e INSEAT FCR :CGE 6-1 SECTICN 6.2.1 0

6. 2.1 Cnsite and Of fsite Organization An oestt, and an offsite ceganization shall to estaolished for unit oceratton and corcorate management. The onsite are offsite organization shall teclude the costtions for activities affecting the safety of the nuclear oower clant.

a. Liees of authority, responsibility and communication shall be established and cefined from the highest management levels l through intermedtate levels to and including all coerating organization positions. Those relationshics shall be documented and updated, as accrocriate, in the form of organizational '

charts. These ergenizational charts will be }

cecumented in the FS1P and updated in accorcance with 10CF RSS.71.

b. There shall be an individual executive cosition in the offstte organization having corocrate resconstbtlity for overall clant nuclear safety. This individual shall take any reasures needed to assure acceptable cerformance of the staff in ocerating, maintainteg, and oroviding technical succort in the plant so that continued nuclear safety is assured.

l

c. There shell be an individual management position an the onsite organization having resoonsthtlity for overall unit operation and l

shall have control over those resources necessary for safe operation ard maintenance of the olant. I

d. Although the individuals who train the ocerating staff and those who carry out the health phystes anc cuality assurance i

functions may recort to the accrocetate manager enstte they shall have sufficient organizational freedom to te incoceedent frem l c:eratteg pressures.

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, . ADMIN!$7tATIVE CONTROLS ,

l E!T_ STAFF (Continued) j

f. Administrative procedures shall be developed and implamentec to limit the workin functions (e.g. ,glicansed ho'Jrs ofSenior unit staff who perform safety-related Operators, licensed Operators, Radiation Protection Technicians, auxiliary operators, and key maintenance personnel),

• fne amourit of overtime worked by unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hour. (Generic Letter No. 82-12).

e, TA s, sh'. f 4 oper tlent m ee n g s m s.f shall hold kle r. Operstors 4. le. t.e s s .

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i CCMANCHE PEAK - UN!T 1 6-2 '

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FIGURE 6.2-1 l

CFF51TE ORGANIZATION CCMANCHE PEAE UNIT 1 6-3

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UNIT ORGANIZATION j

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U TABLE 6.2-1  ;

MINIMUM SHIFT CREW COMPOSITION SINGLE UNIT FACILITY POSITION NUMBER OF IN01VIOUALS REQUIRED TO FILL POSITION MODE 1, 2, 3, or 4 MODE 5 or 6

~

SS l 1 SRO 1 None R0 2 1 A0 2 1 STA 1* None Shift Supervisor with a Senior Operator license on Unit 1 SR0 -

Individual with a Senior Operator license on Unit 1 RO -

Individual with an Operator license on Unit 1 A0 -

Auxiliary Operator STA -

Shift Technical Ad91sor The shif t crew composition may be one less than the minimum requirements of Table 6.2-1 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 shif t crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Supervisor from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with a valid Senior Operator license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

4 "The STA position shall be manned in MODES 1, 2, 3, and 4 unless the Shift Supervisor or the individual with a Senior Operator license meets the qualifications for the STA as required by the NRC.

COMANCHE PEAK - UNIT 1 6-k 3 .

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ADMINISTRATIVE CONTROLS -

6.2.3 !NCEPENDENT SAFETY ENGINEERING GROUP (!$EG)

FUNCT!CN 6.2.3.1 The ISEG shall function to examit.a unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and uther sources of unit design and coerating experience information, facluding units of similar design, which may indicate areas for improving unit safety. The !$EG shall make detailed recomunendations for revised procedures, eouipment modifi-cations, mainterance activities, operations activities, or other means of improving unit safety to the vice President, Nuclear Operations.

COMP 0517!0N .

6.2.3.2 The !$EG shall be composed of at least five, dedicated, full-time engir,eers located on site. Each shall have a bacnolor's degree in engineering or related science and at least 3 years professional level experience in nis field.

RESPONS!81LITIES, 6.2.3.3 The ISE0 shall be responsible for scintaining surveillanca of unit activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as much as practical.

RECOROS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to Vice President, Nuclear Operations.

6.2.4 $N!FT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor (STA) shall provide advisory technical succort to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have rt.ceived specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum quali-fications of ANSI-N14.1-1971 for comparable positions, except for the Radia-tion Protection Manager ** who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager. The licensed Operators and Senior Operators shall also meet or exceed the mi.11 mum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.(Pes., to =ttty tw estaW tim .6 wii Nia.i . n rs, pers ust ~q u 6rsiuJ t. prio p h (: .

ha,$ts ed w;Il he W 4:sJ to ptr h theis b skg NJpgggg "Not responsible for sign-off function.

"Until the Radiation Protection Manager meets all Qualification per R.G 1.3.

Septemoer 1975, an individual wno meets all those qualifications small succort the Radiation Protection Manager.

-E ,m - UNn 1 I e-u -

. ADMIN!$7RATIVE CONTROLS i i

UNIT STAFF QUALIFICAT!0NS (Centinued) l 6.A TRAINING

• 6.4.1 A retraining and replacement training program for the unit staff shall be saintained under the direction of the Vice President Nuclear Operations and shall meet or exceed the requirements and reconnendations of ANSI-N18.1-1971 and Appendix A of 10 CFR 55 and the supplemental reautrements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include f amiliarization with relevant industry opera-tional experience.

6. 5 REVIEW AND AVOIT -

6.5.1 $ TAT!0N OPERATIONS REV!EV COMMITTEE (50RC)

FUNCTION

6. 5.1.1 The $0RC shall function to advise the Vice President, Nuclear Operations on all matters related to nuclear safety, i

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ALTERNATES

, 6.5.1.3 "' .1:e. a;;; ,;;;r. ;h;i' ;; ;;;;in;;; in ritin; ;j the ;000 Ch;i r;;n ;; ;.r;; :n ; ;;;;;rery ::;i;, n;;;;;r, sore than two alternates ({)

shall participate as voting noncers in 50RC acti ities at any or.e time.

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C0KANCHE PEAA - UNIT 1 6-1 T .

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6. !. : . 2 The 50RC shall be ecmoosed of .*anagers or Su:ervisors recorting cirectly to Managers fecm the )

l ce:artments/ sections listed below 1 0:erattens Paintenance i Instrumentation and Controls Technical Sucoort Radtation Protection Quality Assurance Ernergency D1anning Security l l

Testing l

The Manager, Plant Ooerations shall serve as the chairman of  !

l 30RC. 4 senior health onysteint is accootable for the i

tactation Protection Section SORC reoresentative. The j members and their alternates, including the alternate for 1 t9e enateman, snall be designated, in writing, by the Vice

restcart. , Nuclear Ocerations.

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,AOMINISTRATIVE CCNTROLS MEETING FREQUENCY 6.5.1,4 The 50RC shall meet at least once per calendar month and as convened by the 50RC Chairman or his designated alternate.

QUORUM

6. 5.1. 5 The quorum of the 50RC necessary for the performance of the 50RC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and hwt memoers @l including alternates. .

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RESPONS!BILITIES 6.5.1.6 The 50RCpeuunsos..d..tu shall be respons.ible for:

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4. Review of a11 3 5tation Administrativ: "r::: e ::; i

b. Review of the safety evaluations for: (1) procedures, (2) change to procedures, equipment, systees or facilities, and (3) tests or experiments comoleted under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question; l

c. Review of proposed procedures and changes to procedures, equipment, systems or facilities which aey, involve an unreviewed safety ques-tion as defined in 10 CFR 50.59 or involves a change in Technical Specifications; @l 1

d. Review of proposed test or experiments which may, involve an @l unreviewed safety question as defined in 10 CFR 50.59 or requires a change in Technical Specifications;

e. Review of proposed changes to Technical Specifications or the Operating License;

f. Investigation of all violations of the Technical Specifications including the fonvarding of reports covering evaluation and recem- )

sendations to prevent recurrence to the Vice Presidiint, Nuclear 1 Operations and to the Oe.C- l

g. Review of reports of operating abnormalities, deviations from ex-  !

pected performance of plant equipment and of unanticipated defici-encies in the design or operation of structures, systems or components that affect nuclear safety; i h. Review of all REPORTABLE EVENTS;

i. Review of the Security Plan and shall sucait recomended changes to the CRC; CCHANCHE PEAK - UNIT 1 6-16

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ACMINISTRAftVE CONTROLS RESPONS!8!LITIES (Continued)

j. Revidw of the Emergency Plan and shall submit recormended changes to the CRC; y , , , , , , , , , , , , , _,, , , , ,

k. Review of changes to the PROCESS CONTROL PROGR#8,gue 0FFSITE 00SE CALCULATION MANUAL, and Radwaste Treatment Systems; b

1. Review of any accidental, unplanned or uncontrolled radioactive release including tne preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President, Nucletr Operations, and to the ORC;

m. Review of Unit operations to detect potential ha:ards to nuclear safety; ame.

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n. Investigations or analysis of special subjects as requested bL the Chairman of the OR:

ortheVicePresident,NuclearOperationg; @l Review of the Fire Protection Program and revisions theretoj amd g l 6.5.1.7 The 50RC shall:

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a. a Recommend in writing to the "f:: r::fd:nt, ';;?::r ^ :::ti: : approval or disapproval of items considered under Specification 6.5.1.6a.

through eg ! , j , h, :-d ' b: :, prior to their iriplementation; glI

b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a, through e. and s.

constitutes an unreviewed safety question; and c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Executive Vice President-Nuclear Engineering and Operations and the Operations Review Committee of disagreeeent eetween the 50RC and the -V4+e--

'r::t d:nt, "u:!::r ^ :r:ti:n:; however, the Vice President, Nuclear g

, Operations shall have responsibility for resolution of such dis-agreements pursuant to Specification 6.1.1.

RECORUS desy.l.J .me. n uhyg Qu 4.c$s. A u $

6. 5.1. 8 The 50RC shall maintain written sinutes of each 50RC meeting that, at a sinimus, document the results of all SORC activities performed under the responsibility provisions of these Technical Specifications. Copies shall te provided to the Vice President Nuclear Operations and the Operations Review Comi t,t e e.

k' 's4 o S O s. 7"s<.W e,l Sp g,,,;g ; ,

ud e se:s:m ny "V * * * N h*1" i

i C:MANCHE PEAK - UNIT 1 6\7 .

i 1

l ADMINISTRATIVE CONTROLS nMF L l"

__ l 6.5.2 OPERATIONS REVIEV _CCm!TTEE (0RC)

FUNCTION l

6.5.2.1 The CRC shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry,  !

d. Metallurgy,

s. Instrumentation and control,

f. Radiological safety, f

g. Mechanical and electrical engineering, and .

h. Quality assurance practices. I The CRC shall report to and advise the Executive Vice President, Nuclear Engineering and operations on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8. i COMPOSITION 6.5.2.2 The ORC shall be composed of at least five individuals of whom no more than minority are members having line responsibility for operations at CPSES. The chairman and all members will be appointed by the Executive Vice President, Nuclear Engineering and Operations.

The ORC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a sinimum of 5 years technical experience. It is the responsibility of the Chairman to ensure experience and competence is available to review problems in areas listed in 1 Specification 6.5.2.la, through h. To a large measure, this er.cerience and competence rests with the mentorship of the ORC. In specialized areas, this experience say De provided by personnel who act as consu1* ant,s to the ()RC.

ALTERNATES 6.5.2.3 The Alterante for the Chairman and all alternate meneers shall be appointed in writing by the Executive Vice. President, Nuclear Engineering and Operations to serve on a temporary basis; however, no more than two alter- i nates shall participate as voting members in CRC activities at any one time. I l

CCKANCHE PE 4 - UNIT 1 6-h i ,

~

ACMIN!$7 RAT!VE C0hTROL$

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determired by the Chairman, CRC to provide expert advice to the CRC.

WEET!NG FREQUENCY 6.5.2.5 The CRC shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 sonths thereafter.

QUORUM 6.5.2.6 The quorum of the ORC necessary for the performance of the ORC review and audit functions of these Technical Specifications shall consist of not less than a majority of the appointed individuals (or their alternates) anc the Chairman or his designated alternate. No more than a minority of the quorum shall have line responsibility for operation of the unit.

Rt.y!EW 4.5.2.7 The ORC shall be responsible for the review of: I

a. The safety evaluations for: (1) changes to procedu es, equipment, or systems; and (2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;

b. Proposed changes to procedures, equipment, or systees which involve an unreviewed safety question as defined in 10 CFR 50.59; c.

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.

Proposed changes to Technical Specifications or this Operating License; e.

Violations of Codes, regulations, orders Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety;

g. All REPORTA8LE EVENT 5; 1

h.

All recognized indications of an unanticipated deficiency in some ,

aspect of design or operation of structures, systems, or components l that could affect nuclear safety; and  !

i. Reports and meeting sinutes of the 50RC.

1 CCMANCHE PEA ( - UNIT 1 4 5-K 9

• i

1. - -. - ,- ~ .,-,-

. . l ADMIN!$TRATIVE CONTROLS AUO!TS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the CRC. The audits shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified interval provided the combined time interval for any three consecutive intervals shall not exceed 3.25 times the specified interval. These audits shall encompass:

t

a. The conformance of unit operation to provisions contained within the l Technical Specifications and applicable license conditions at least once per 12 months;

b. The performance, training, and qualifications of the entire unit staff at least once per 12 months;

. c. The results of actions taken to correct deficiencies occurring in i unit equipment, structures, systees, or method of operation that i affect nuclear safety, at least once per 6 months;

d. The performance of activities required by the Operational Quality  !

Assurance Program to meet the criteria of Appendix 4, 10 CFR 50, at least once per 24 months;

)

l

e. The fire protection prograsumatic controls including the isolementing i procedures at least once per 24 months by qualified licensee QA personnel;

f. The fire protection equipment and program implementation at least once per 12 months utilizirq either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year; pg,g 'A g. h

'.m:__":_di:1:;i::1

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. n't:r'r; " :; = r: th: r:: !!: gg

) h. The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at j least once per 24 months;

1. The FR0 CESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; l j. The performance of activities required by the Quality Assurance Program for effluent and environmental sonitoring at least once per 12 months; w e

@ i j k. Any other area of uni' operation considered appropriate by the  !

ORC or the Executive

• resident Nuclear Engineering and Operation % J @

t 3

nsur T y 6 j CCMANCHE PEAK - UNIT 1 6h10 '

l

- - - - - - - - - + - .

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l, .

INSERT 3 FOR NEW C AGE 6-19 CLD 6-12) SECTION 6.5.2.4 I "A" l

i

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• me :erformance of activities in accoreance with the '

l 3ADICACT!VE E:'LLENT AND E W!RCNMENT A MON!TCRING j 'ANUAL at least once oer 24 months

]

s 4

age i 1

4 N

i i

1. The performance of activittee reeutred by the Technical Spectf tcation Imorovement Program at least once oer 24 .

! ecnths.

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. . I ADM!N!STRAT!VE CONTROLS l

RECOR05 6.5.2.9 Records of ORC activities shall be prepared, approved, and distribu-ted as indicated below:

4. Minutes of each ORC meeting shall be prepared, accroved, and for-warded to the Vice President, Nuclear Operations and Executive Vice President, Nuclear Engineering and Operations within 14 days following each meeting; I

b. Reports of reviews encompassed by Specification 6.5.2.7 shall be I prepared, approved, and forwarded to the dice President Nuclear '

operations and Executive Vice .' resident Nuclear Engineering and i Operations within 14 days following completion of the review; and l

c. Audit reports encompassed by Specification Cs5.2.8 shall be for-werded to the Vice President, Nuclear Operations and Executive Vice  !

President Nuclear Engineering and Operat*arr ar4 to the sanagement positions responsible for the areas audited within 30 days after completion of the audit by the auditing organizatica.

6.5.3 TECHN!CA', REV!EV AND CONTR01.5 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

I

a. Procedures required by Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared,

reviewed and approved. Each such procedure or procedure change i shall be reviewed by a qualified individual / group other than the j individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change. The Vice Presi-dent Nuclear Operations, shall approve Station Administrative Procedures, Security Plan Implementing Procedures, and Emergency

] Plan Implementing Procedures. Other procedures shall be approved by 1' the appropriate approval authority, as designated by the Vice Presi-dent, Nuclear Operations, in writing. Individuals responsible for procedure reviews shall be members of the Nuclear Operations Staff previously designated by the Vice President, Nuclear Operations.

Changes to procedures which do not change the intent of approsed procedures may be approved for impleeentation by two members of the 1

.tuclear Operations Staff, at least one of whoe holds a Senior j Operator License, provided such approval is prior to implementation j

and is documented. Such changes shall be approved by the original approval authority within 14 days of implementation;  !

( b. Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications shall be prepared, reviewed, and 1

i 1

) CcMANCHE PEAK - UNIT 1 6 'b{ l[

• l

U g eq B OQ U .i . ,

s ADMihiSTRATIVE CONTROLS TECHNICAL REVIEW AND CONTROLS (Continued) approved. Each such test or experiment snal' te reviewed by a qualifico inoivioual/ group other than the individual / group which prepared the proposed test or experiment. Proposed test and exceri-ments shall be approved before implementation by the Manager, Plant Operations. Individuals responsible for conducting such reviews shall be members of the Nuclear Operations Staff previously designated by the Vic, # resident, Nuclear Operations;

c. Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall ce reviewed as designated by the Vice President, Engineering and Construction. Each such modification shall be reviewed by a qualified individual / group other than the individual / group which designed the modification, but who say be from the same organization as the individual / group which designed the modifications. Individuals / groups responsible for conducting such reviews shall be previously designated by the Vice President, Engineering and Construction. Proposed modifica-tions to plant nuclear safety-related structures, systems and

• components shall be approved by the Manager, Plant Operations prior to implementation;

d. Each review conducted in accordance with the requirements of Spect-fications 6. 5. 3. la, 6.5. 3. lb, and 6.5. 3.1c, shall include a deter-aination of whether or not additional cross-disciplinary review is neces sa ry. If deemed necessary, such review shall be done in accordance with the appropriate qualification requirements;

e. Each review shall include a cetermination of whether or not an unreviewed safety question is involved. Pursuant to NRC approval i

of itees involving unreviewed safety questions shall be obtained i

prior to the Manager, Plant Operations, approval for implementation; and

f. The Security Plan and Energency Plan, and implementing procedures, shall be reviewed at least once per 12 months. Recommended changes to the implementing procedures shall be approved by the ";n:;;e3

• i "!::t 0;:r:tt:::. Recommended changes to the Plans shall be ({)

l reviewed pursuant to the requirements of Specifications 6.5.1.6 and

6.5.2.8 and approved by the "

::;:r, "!:nt 0;: :t!:::. NRC approval (3) shall be obtained as appropriate, t u bu; At, u. .. e , twg 6.5.3.2 Records of the above activities described in 6.5.3.1 shall be provided to the Vice President, Nuclear Operations, 50RC, and/or ORC as necessary for required reviews.

6. 6 REPORTA8LE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA8LE EVENTS:

a. The Cen41ssion shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73 and i b. Each REPORTABLE EVENT shall be reviewed by the 50RC, and the results of this review small be suositted to the ORC and the Vice President Nuclear Operations.

1 CCMANCHE PEAK UNIT 1 6-14 12, '

BRT AOMINISTRATIVE CONTROLS 6.7 SAFETY t.!MIT VIOLATION

6. 7.1 The following actions shall be taken in the event a Safety Limit is violatec:

a. In accordance with 10 CFR 50.72, the NRC Operatiens Center, shall be notified by telephone as soon as practical and in all cases within one hour after the violation has been determined. The Vice President, Nuclear Operations and the Operations Review Coeunittee (ORC) small be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. A Licensee Event Report shall be prepared in accordance with 10 C80 50. ."4.

c. The License Event Report shall be subettted to the Commission in accorcance M to tht with 10 CFR 50.73,,Vice President, Nuclear Operations.and 4he 0ceraticas$

Review committee (ORC) within 30 days after discovery of the event. -

ss.t:.s cose t'... a s.:w c.. .a e s uea,.\--

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

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

a. The applicable procedures recoemended in Ar.pendix A of Regulatory Guide 1.33. Revision 2, February 1978;

b. The emergency operating procedures required to implement the require-ments of NUREG 0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33;

c. Security Plan (selementation;

d. Emergency Plan inglewntation;

e. PROCESS CONTROL PROGRM implementation;

f. OFFSITE DOSE CALCULATION MANUAL implementation; .4ae-g g.

Im a.r ,A . QualityAssuranceforeffluentandenvironmentalmonitorich;

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CCMANCHE PEAK - UNIT 1 6 Kl3

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. o INSERTS FOR NEW PAGE 6-13 (OLD 6-15) SECTIONS E.S.! f. E. 5.1 i

,. p ., ,

{

9 3ADICACT:VE I.:FLLENT AND ENVIRONMENTAL .*0NITORING l VANUAL imolementattoni i

9 f:tre Cretect Aroccam smolernentations ano l

1. Tecnnteal Scectftcation Iraerovernent Program imolemoetat1on.

(  :

.gu I

6. S. 2 Eacn orecedure and administrative policy of I

3:ecification 6.8.1 above, and changes thereto, shall be '

reviewed and accroved ortoe to implementation as set forth

'n 5:ecification 6.5 above.

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4 1

1 i

, e ACMINISTRATIVE CONTRC.5 _

PROCEDURES ANO ptoGRAMS (Continued)  !

%%: th:r;:* !: d: r ent M , C'/f 1 :1 b; th ? CEC, trd ::r:;;d ty tN

'?' : r ;i d:7.t. %:1:07 C Cr ti:n; uttn'--l' dej: c' t ;;!:::nt::::n g i 6.8 53 The following programs shall be established, implemented, and maintained: @l

a. Primary coolant Sources Outside Containment ,

A program to reduce leakage free those portions of systems outside 1 containeent that could contain highly radioactive fluids during a serious transient or aqcident to as low as practical levels. The

. systees include the post accident recirculation portions of the '

Containment Spray Systee, Safety Injection System, Chemical and volume Control Systee, RHR Systee, and RCS Sampling Systes (Post ,

Accident Sampling Systes portion only). The program small include the following:

1) Preventive maintenance and periodic visual inspection require-ments, and

2) Integrated leak test requirements for each systee at refueling I cycle intervals or less,

b. In Plant Radiaiion Monitorino l

1 A program which will ensure the capability to accurately determine l the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1) Training of personnel,

2) Procedures for monitoring, and

3) Provisions for saintenance of sasoling and analysis equipment.

c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generater tube degradation and low pressure turbine disc stress corrosion cracking. This program small include:

1) Identification of a sampling schedule for the critical variaeles and control points for these variables, I

2) Identification of the procedures used to measure the values of trie critical variables. l

3) Identification of process sampling points, which shall include i

)

monitoring the discharge of the condensate pumps for evicence i of condenser in-leakage,

4) Procedures for the recording and management of data,  !

1

\

I 5) Procedures defining corrective actions for all of f control point cnesistry conditions, and i

WACHE PEM - WIT 1 6-h N '

.

• ACMINT$7RATIVE CCNTROLS l

Pe0CE0VRES AMO Pe0 CRAMS (Continued) i

6) A procedure identifying: (a) the authority responsible for the

' interpretation of the data, and (b) the sequence and timing of amministrative events required to initiate corrective action,

d. Post accident Samoling A program which will ensure the capability to obtain and analyze l reactor coolant, radioactive f odines and particulates in plant i gaseous effluents. and containment atmosphere samples uncer acctcent l 1

conditions. The program shall include the following:

1) Training of personnel, l

2) Procedures for sampling and analysis, and

3) Provisions for maintenance of sampling and analysis equipment, I

e. RADIQACTIVE EFFLUDfT AM ENVIR0004DifAl MONITORIht MANUAL (REDet)

! I The RADICACTIVE EFFLUENT ANO ENVIR0fMENTAL MONITORING MANUAL l (RIDM) shall outline the effluent and environmental sampling and t

analysis program used to deterstne the concentration of radioactive materials in those pathways which lead to radiation

' exposures to MEMBER (Sp 0F THE PUSLIC from routine station operation. The manus, provides the following:

l 1) Input to the OFFSITE DOSE CALCULATION MANUAL (00CN) methodologies for calculating liquid and gaseous effluent j concentrations and offsite doses, 1

' 2) Guidelines for operattnq radioactive waste treatment

• ** ,W ' rystems. in"order that sffstt4:deses will be'kept as low as reasonably achtuable (ALARA),

3) Definition of the Radiological Environmental Monitoring Program (RDtP), which provsdes. conf treation that . -

1 concentrations of radteactivesatorial released from CPSES are not higher than expected,

' 4) An outline of information required to be submitted to the l NRC through the Seelannual Radioactive Effluent Release  !

Report and tie Annual Radiological Environmental Operating l Report, and l J

l

5) Administrative requirements for implementation, including j the review anil approval' process for the manual and changes j thereto.

l

! c: m c a ein - u it 1 sw .

. . i AONINISTRATIVE CCNTROLS 6.9 REPORTfhG REQUIREMENTS ROUT!NE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, code ,

of Federal Regulations, the following reports shall be submitted to the Regional l Administrator of the Regional Of fice of the NRC unless otherwise noted.

l $7ARTUP REPORT l l

l 6.9.1.1 A summary report of plant startup and power encalation testing small be subattted following: (1) receipt of an Operating License (2) amenoment to the license involving a planned increase in power level. (3) installation of fuel that has a different design or has been manufactured by a different fuel I supplier, and (4) modifications that may have significantly altered the nuclear,

! theriaal, or hydraulic performance of the unit.

I. The initial Startup Report shall address each of the startup tests identi-i fied in Chapter 14 of the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteris-1 tics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to comonstrate the acceptability l of changes and/or modifications.

• i I Startup Reports shall es submitted within: (1) 90 days following l completion of the Startup Test Program, (2) 90 days following resumption or i connencement of comunercial power operation, or (3) S months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startuo Test Program,

.: and resumption or commencement of coamercial operation), suoplementary reports small be submitted at least every 3 months until all three events have been ccepleted.

ANNUALR(PORTS

• I

6. 9.1. 2 Annua) Reports covering the activit hs of the un't as described below 1

for the previous calendar year shall be submittsd prior to March 1 of each ysar. The initial report shall be subeitted prior to March 1 of the year

following initial criticality. l l

1 Reports required on an ar.nual basis shall include:

a. A tabulation on an annual basis of the numeer of station, utility, and other personnel (including contractors) receiving exposures 1 'A single sucaittal may be made for a sultiple unit station. The submitta) snculd comoine those sections that are cc mon to all units at the station,

] CCMANCHE PEAK UNIT 1 6-it f(, *

, -__,_.__s _ _ _ _ _ _ . _ _ _ - . _ _ _ _ . , . _ . . . _ . . _ . , _ . , _ . _ _ _ - . _ . _ . , _ _ . , , _ _ . - _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ . _

~

l

. . i ACM!N!$TRAT!VE CONTROL $_

{

ANNUAL REPORTS (Continued) greater than 100 area /yr and their associated man ree exposure according to work and job functions

• e.g. , reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe saintenance), waste processing, and refueling.

The dese assignments to various duty functions may be estbaated based on pocket dosimeter, thersoluminescent dosimeter (TLD), or .

film badge measurements. $st'l exposures totalling less than 20% l of the individual total dose need not be accounted for. In the i aggregate, at least 80% of the total whole-body dose received frem external sources should be assigned to specific major work functions;

b. The results of specific activity analyses in which the primary coolant exceeded the Itaits of Specification 3.4.4. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radio-iodine performed prior to exceeding the Itait, results of analysis while limit was exceeded and results of one analysis after the radio-iodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiofocine concentrations; (3) Cleareup flow history starting 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> prior to the first sample j in which the limit was exceeded; (4) Graph of the I-131 concentra- ,

tion (WC1/gn) and one other radioidine isotope concentration (WCi/ge) l as a function of time for the duration of the specific activity above l the steady-state level; and (5) The time duration when the specific activity of tht primary coolant exceeded the radiciodine limit.

ANNUAL RA0!0 LOGICAL ENVIRCle4(NTAl. OPERATING REPORT **

6.9.1.3 Routine Annual Radiological Environmental Operating Reports covering i i

the operation of the unit during the previous calendar year shall be cubmitted prior to May 1 of each year. The initial report shall be subettted prior to May 1 of the year fo11 ewing initial criticality and shall include copies of l reports of the preoperational Radiological Environmental Monitoring Program of

• • .hthe unit for at least two years prior to initial criticality. TAsse. rerrts g

% 4sthe.t ini m.d k <*en ne.ded in us Artmm.

N ' n =1 Sc h h;i ni =tr: n nt:1 0;;r:ti g t;;rt; :h:11 i :!;::

r :rin, St: pr:t thn;, ::: en-:cly:S 01tr:n= ;fth; r:=it: Of th; c::bh;h:1 r? rr=n:1-:n:P hn= ::thitin hr it; ::; r t ;rt:c,

• This tabulation supplements the requirements of 500, t0? :f 10 CFR 20MO7.

• • A single submittal say be made for a multiple unit station.

CCKANCHE PEAK UNIT 1 6- M 17

AOMIN!$T UTIVC CONTROLS n u n.  :

l t'). * ^"10' 4GMAk-4W14GNunTAt-0*P!"0 *!.*O*? 'Snt he.e ,

inc ing a comparison with preoperational studies, with operational cent s, i as appr riate, and with previous environmental surveillance reports, an  !

assessmen f the observed impacts of the plant operation on the env onme nt.

Tne report:

Specification 11 also include the results of the Land Use Census quired by

. .2. 1 i

l

. The Annual Radi gical Environmental Operating Repor. shall include the results of analysis of l 1 radiological environmental s les and of all  !

environmental radiation me urements taken during th eriod pursuant to the i locations specified in the t e and figures in t Offsite Dose Calculation Manual, as wil as summarized a tabulated res s of these analyses and ,

measurements in the forset of the le in t Radiological Assessment Branch j Technical Position, Revision 1, Nov r' 9. In the event that some indivi-dual results are not available for inc1 'on with the report, the report shall be submitted noting and explaining t rea s for the missing results. The g missing data shall be subettted a con as po ible in a supplementary report.

The reports shall also lude the following: summary description of j the Radiological Enviro al knitoring Program; at est tw legible maps *

covering all sampling 1 ations keyed to a table diving stances and airections from the centerline one reactor; the results of license articipation in the Interlaborato onparison Program and the corrective act b taken if the l specified prot- is not being performed as required by Specific ion 3.12.3; reasons for conducting the Radiological Environmental m nitorin Program as required b specification 3.12.1, and discussion of all deviations fr the samplin schedule of Table 3.121; discussion of environmental sample me re-nent hat exceed the reperting levels of Table 3.12-2 but are not the resu i of ant effluents, pursuant to ACTION b, of Specification 3.12.1; and discuss' n i

.-:!' : :!y;;: " we.h h tM-LLO r; p r;d by 40 4 '.1P 1 .;; n;; ;;hi;vetie.-

I SEM! ANNUAL 0010ACTIVEEFFLUENTRELEAstREPORT*\ b, 6.9.1.4 Routina Seetannual Radioactive Effluent Release Reports covering the

! operation of the unit during the previous 6 months of operation shall be I

subeitted within 60 days af ter January 1 and July 1 of each year. The period of the first epo t shall be i

4

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f stcLulW4 A(8 4 j "One :; ;h 4-tever-$tet4;n; n'er ti4@b%S**", e ;;;;nd in& inci.;;

e- ---- Me4eet-14 eir4+e+.

\*A single submit.tal say be made for a multiple unit station. The submitt,a1 g should concine those sections that are common to all units at the stationi

) nc=ever, for units with separate raevaste systees, the subatttal small specify the releases of ractoactive saterial free each unit.

4 C0KANCHE PEAK UNIT 1 6-h it .

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O A,p44!N!$7RATIVE CONTROLS 4(*t'TL i'004074V(--EfMWMT-^!LUK- E~T (h@4 s arized on a quarterly basis following the format of Appendix 5 thereof

/

For olid wastes, the format for Table 3 in Appeneix I sna11 be supplemen ed with \bree additional categories: class of solid wastes (as defined by 0 CFR Part 6 , type of container (e.g. , LSA, Type A. Type 8. Large Quantity and

$0LIO!FI T!ON agent or absorbent (e.g. , cement, ures formaldehyde).

The 5 tannualRadioactiveEffluentReleaseReporttobesuba)tedwithin 60 days aft January 1 of each year shall include an 4nnual susmary of hourly meteorologica data collected over the previous year. This son 1 susenary may be either in t fors of an hour-by hour listing on magnetic t e of wind speed, wind direction, spheric stability, and precipitation (if esured), or in the fore of joint requency distributions of wind speed, wi direction, and atmospheric stabili .

• This same report shall include a assessment of the radiation doses due the radioactive liquid and gaseou effluents released from the unit or stati during the previous calendar y ar. This same report shall also include an a essment of the radiation dos from radioactive liquid and gaseous effluents to MSERS OF THE PUOLIC due t their activities inside the $1TE BOUNCARY (Figure .1-3)) during the rope period. All assumptions used in making these assess nts, i.e., specific tivity, exposure ties, and location, shall be included i these reports, e seteorological conditions concurrent with t.he time of re ase of radioac ve seterials in gaseous efflu-

)

ents, as determined by sampling equency in seasurement, shall be used for determining the gaseous pathway do es. The ssessment of radiation doses shall i be performed in accordance with the the ogy and parameters in the OFF5!TE CCSE CALCULATION MANUAL (00CM).

i

! The Seeiannual Radioactive Efflu Release Report to be subeitted within t

60 days after January 1 of each year shal also iaciude an assessment of radia-t tion doses to the likely most expo d MEMS OF THE PUSLIC free reactor releases and other nearby uranius fuel cyc sources, including doses froe primary efflu-J . ent pathways and direct radiatt , for the pr tous calendar year to show con-t forsance with 40 CFR Part 190 Environmental R iation Protection Standards for 1 Nuclear Power Operation." A estable methods to calculating the dose contribu-l tion froe liquid and gaseoue affluents are given i Regulatory Guide 1.109, i Rev. 1, October 1977, i

/

The Sosiannual Ra osct.tv6 Effluent Release Repor shalt include a list a

4 and description of u anned releases from the site to ESTRICTED AREAS of radioactive A terial in gaseous and liquid affluents sad during the reporting

) period.

The $eetan al Radioactive Effluent Release Reports'shal include any j changes made d ing the reporting period to the PROCESS CONTROL ROGRM (PCP)

I

) In iieu ff.iuesission witn the seetannuai Radioactive Effiuent Reie e Report /the licensee has the option of retaining this suesnary of rega red

! seteo logical data on site in a file that shall be provided to the NR

! uno request.

l c==C spx - WT 4 C R+. .

! l i 1

i o

ADN!NISTRATIVE CONTROLS i

.1" ? m '?'. "." M f Ti"' !"WEMT-4ME *!! "i"^" '0:nt i n.;;) .

and to th $1TE 00$E CALCULAT!0N MANUAL (00CN), pursuant to so fica-tions 4.13 ane . respectively, as well as any major chan o L.iquid. .  ;

Gaseous, or Solid Ra e Treatment Systems pursuant cecification 6.15.

It shall also include a 1 of new locations dose calculations anc/or environmental monitoring identi the use Census pusuant to $pecif t-cation 3.12.2. @i The See1 annual Radio e Effluent Release is shall also include the following: an e ation as to why the inoperact f liquid or gaseous effluent acnit instrumentation was not corrected within ime specifica in Specif on 3.3.3.10 or 3.3.J.11, respectively; and descriptt the eve ending to liquid holdup tariks or gas storage tants exceeding the

,:tt: ;f %:;ifi;;ti;; 3.11.1.t ;r 3.-11.J.?, r;;;;;tively.

MONTHL,Y OPERATING REPORTS

6. 9.1. 5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, 1 shall be subeitted on a monthly basis to the Director, Office of Resource l Management U.S. Nuclear Regulatory Coeusistion, Washington 0.C. 20555, with a l copy to the Regional Administrator of the Regional Office of the NRC, no later l than the 15th of each month following the calender month covered by the report.

8A0!AL PEAKING FACTOR 1.!MIT REPORT

6. 9.1. 6 The F,y limits for RATED THERMAL PCW R (F") shall be established for at least each reload core and shall be maintained available in the Control Rece. Tne limits shall be established and implemented on a time scale consis-tant with normal procedural changes.

The analytical methods used to generate the F,y limits shall be those previously reviewed and approved by the NRC.h !f changes to these eethods are

'*end necessary they will be eval sted in accordance with 10 CFR 50.59 and gl sucaitted to the NRC for review ano approval prior to their use if the change is deta'eined to involve an unreviewed safety question cr if such a change would require amendment of previously subettted cocumentation. I A report containing the F,y limits for all core planes cantaining Bank "0" control rods and all unrodded core planes along with t.he plot of predict.ec l rel a.xial core height (with the limit envelope for c:moarison) shall F

• P be provided to the NRC OccuM nt Control delt wit.h coctes to the Regional Acmin. l istrator and the Resicent Inspector within 30 days of their isole=entat. ion.

i i

II 3)$' ^ ";i; T N %P4)v%4e&-de*i7$d 0,"4 (;;C 3II;,-Ing ?res;4,7;i' -; 4 -d12

-4U4h444*g** wee 4*4eae-Se4ety-i W4;n ";tn;c;1;g. ' '

CCMANCHE PEAK - (N!T 1 6 M ji , )

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1

. s l ADMINISTRATIVE CONTR01.5

',' _ iPORTS I acist reports shall be submitted to the Regional Administrator cf the Jffice of the NRC within the time period specified for each report.

t_ <ECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level; i

b. Records and logs of principal maintenance activities, inspections, '

repair, and replacement of principal itses of equipment related to nuclear safety;  !

c. All REPORTA81.E EVENTS; l i

d. Records of surveillance activities, inspections, and calibrations required by e::: TechnicalSpecifications? : gl e.

os Records of changes made to the procedures requirad by Specification 6.8.1;

f. Records of radioactive shipments;  ;

g.

Records of sealed source and fission detector leak tests and results; I and

h. Records of annual physical inventory of all sealed source material of record. I 1

a he.1 Spe.;f:e 4,w Lprovtaf /by*m, Fmt Arolset h Progm ud Ras soAe. rove 1FFt.Jw'r Mk KNvotoamEdnL monorosws m' aunu, sac.spt as e.spl;a.: bly covse sd i n Sp tc.* hie d ten (, . s o . 3

(,CMANCHE PEAK - UNIT 1 6-h),o '

- _ . _ . - - - - . - - . - _ , . _ _ _ _ . _ _ , . _ _ - , - - - . - - . _ . - - . - _ _ - - - . _ . ~ _ - - - -

o DRE ADMINISTRATIVE CONTROLS RECORO RETENTION (Continued}

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a. Records arid drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report;

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

c. Records of radiation exposure for all individuals entering radiation control areas;

d. Records of gaseous and itquid radioactive material released to the environs;

e. Records of transient or operational cycles for those unit components identified in Table 5.7-1;

f. Records of reactor tests and experiments;

g. Records of training and qualification for current acabers of the unit staff;

h. Records of inservice inspections performed pursuant to these Technical Specifications;

,, ,,.f d.'n M s

1. Records Assuranc,of quality assurance activities n ; i, gby t'a Quality e Manual; @

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;

k. Records of meetings of the 50RC and the ORC;

1. Records of the service lives of all hydraulic and mechanical snubbers required by 0;,;;ifi;;ti;r. 0.7,0 including the date at which the service life"commences and associated installation and @

maintenance records; tu re w ) op.<M.s 6 % .upe...

t pr. m

m. Records of secondary water sampling and water quality; and

n. Records of analyses required by the Radiological Environmental i4cnitoring Program that would permit evaluation of the accuracy of i the analysis at a later date. This should include procedures  !

effective at specified times and QA records showing that these l procedures were fo)1 owed. '

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be approved, maintataed, and i adhered to for all operations involving personnel radiation exposure.

l l

COMANCHE PEAK - UNIT 1 6-h 21 a

u a ,

AtWINISTRATIVE CONTROLS DRE 6.12 HIGH RADIATICM AREA 6.12.1 Pursuant to paragraph 10 CFR 20.203(c)(5), in lieu of the "control device" or "alar 1m signal" required by paragraph 10 CFR 20.203(c), each nigh radiation area, as defined in 10 CFR 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) 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). Indi-viduals qualified in radiation protection procedures (e.g., Radiation Protec-tion Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the puformance of their assigned duties ir high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protec-tion 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 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 estab-lished and personnel have been made knowledgeable of thee; or

c. An individual qualified in radiation protection procedures with a radiation dose rate sonitoring device, who is responsible for pro-viding positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RWP. I 6.12.2 In addition to the requirements of Specification 6.12.1, areas acces-  !

sible to personnel with radiation levels greater than 1000 mR/h at 45 ca l (18 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked doors to prevent unauthorized entry, '

and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or radiation protection supervision. Doors shall remain l

locked except during periods of access by personnel under an approved RWP 1 which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the f.tay tim specification of the RWP, direct or remoto (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radia-tion protection procedures to provide positive exposure control over the acti.ities being performed within the area.

For individual high radiation areas accessible to personnel d tn radia-tion levels of greater than 1000 mR/h that are located within la.me 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, conspicuously posted, and a flashing light shall be activated as a warning device.

CCHANCHE PEAK - UNIT 1 6-h n ,

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l ADMINISTRATIVE CONTROLS nRW' ~

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

a. Shall be submitted to the Cosumission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was

. made. This submittal shall contain:

1

1) Sufficiently detailed information to totally support the rationale for the change without benefit of additional or l supplemental information;

2) A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and

3) Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.

b. Shall become effective upon review and acceptance by the 50RC.

6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated chant t to the 00CM:

a. Shall be submitted .o the u mmission in the Semiannual Radioactive Effluent Release Repor*. for the period in which the change (s) was made effective. This submittal shall contain:

1) Sufficiently detailed information to totally support the rationale for the change without benefit of additional or I supplemental information. Information submitted should consist of a package of those pages of the 00CM te be changed with each -

page numbered, dated and containing the revision number, together with appropriate analyses or evaluations justifying the change (s);

2) A determination that the change will not reduce the accuracy or reliability of dose calculations or Setpoint determinations; and

3) Occumentation of the fact that the change has been reviewed and found acceptable by the $0RC.

b. Shall become effective upon review and acceptance by the 50RC.

.IN S ERT

• A ' --- > b CCMANCHE PEAK - UNIT 1 6-K 2,3 ,

9 a s f s g INSERT FOR NEW PAGE 6-23 (CLD 6-26) NEW SECTION

.g.

6.15 20D199GIlYI.EEELVESI.ESYIB950iSI96_:CSIIQBIS9

!96V96.!!!E551 6.15.1 The REEMM shall me accroved oy the Cemmissten '

orter to smolementation.

6.15.2 Licensee initiated changes to the REEMM

a. Shall be sueettted to the Commissten for amoroval orter to smolementation. This submittal shall I contains i

(1) Suf ficiently detailed information to totally succort the rationale for the change without  !

benefit of additional or supplemental information.

(2) A determination that the change does not reduce the overall effectiveness or reliability of the radiological ef fluent or environmental monitoring orograms.

(3) Documentation of the f act that the enange has been reviewed arid found acceotable by SORC.

o. Shall become effective uoon review and accentance by the Commission

. i

, ,, ADMINISTRATIVE CONTROLS 16 6.1% MAJOR CHANGES 70 LICUIO, GASEOUS, AND SOLIO RA0 WASTE TREATMENT SYSTEMS

• 16 k) 6.11 1 Licensee-initiated major changes to the Radwesta Treatment Systems (liquid, gaseous, and solid):

a. Shall be reported to the Commission in the Semiannual Radioective Effluent R, lease Report for the period in which the evaluation was reviewed by the 50RC. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systees;

4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous affluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MEM8ER OF THE PU8LIC in the UNRESTRICTED AREA 49d to the general population that differ from those previously estimated in the License application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the change is to be made; -

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) 'st tusentation of the fact that the change was reviewed and

, fo,nd acceptable by the 50RC.

b. Shall become effective upon review and acceptance by the 50RC.

"Licensees may choose to submit the information called for in this Specification as part of the annual FSAR update.

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. _ _ , , _ . . _ _ _ _ _ _ . - , - _ _ _ . . _ _ _ _ _ . . . _ , _ _ _ _ _ _ _ _ _ . . , . _ . _ . _ - - . _ _ . _ - _ _ . _ _ _ _ _ . _ _ _ . _ __ .__ . _ . ,