ML20059F403

Comments on TS Sections 4 & 5 for Sys 80+.Markup Copy of Affected TS Encl.Responses to Comments Requested No Later than 2 Wks from Receipt of Ltr

ML20059F403
Person / Time
Site:	05200002
Issue date:	01/07/1994
From:	Shembarger K Office of Nuclear Reactor Regulation
To:	Brinkman C ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
NUDOCS 9401140007
Download: ML20059F403 (17)

Text

.- -.. - - - -

l January 7, 1994 i

i Docket No.52-002 i

Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing Combustion Engineering,.Inc.

4 l

1000 Prospect Hill Road Windsor,-Connecticut 06095-0500-l

Dear Mr. Brinkman:

i

SUBJECT:

COMMENTS ON TECHNICAL SPECIFICATIONS (TS) FOR SYSTEM 80+

The Nuclear Regulatory Commission-(NRC) staff has reviewed Sections 4 and 5 of the System 80+ TS, and the comments are shown on the markup copy of the cffected TS in the enclosure. Provide responses to these comments no.later i

than two weeks from your receipt of this letter to allow us to maintain our.

]

review schedule.

i This affects nine or fewer respondents, and therefore, is not subject-to review by the Office of Management and Budget under P.L.96-511.

l Sincerely, (Original signed by) i Kristine M. Shembarger, Project Manager.

j Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

As stated i

cc w/ enclosure:

l See next page i

1 j

DISTRIBUTION:

40ecket:F11e m PDST R/F DCrutchfield WTravers PDR RBorchardt PShea TWambach XFranovich SMagruder KShembarger WDean, 17G21 j

JMoore, 15B18 ACRS (11) (w/o encl) i 9401140007 940107 A

Om

=

7//

j p

i 0FF:

LA:PDST:ADAR PM:PDST:ADAS PMTPDST:ADA SC:PDST:ADAR i

NAME: PShea ' Q p S KShembarger M 43 MFranovich RArchitzel I

DATE: 01/(.o/94 01/(,/94 01/ 7 /94-01/7/94 f

.j j

k y0f 0FFICIAL RECORD COPY: CELT 0105.KMS t

i NiiC FRE CENTEit f;&PY l

.t20022 j

4

_ -.. _. _ - =

ABB-Combustion Engineering, Inc.

Docket No.52-002 cc: Mr. C. B. Brinkman, Acting Director Nuclear Systems Licensing ABB-Combustion Engineering, Inc.

1000 Prospect Hill Road 1d Windsor, Connecticut 06095-0500 p-,]i Mr. C. B. Brinkman, Manager

~

Washington Nuclear Operations ABB-Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stan Ritterbusch Nuclear Licensing ABB-Combustion Engineering 1000 Prospect Hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.

20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Washington, D.C.

20503 Mr. Rayr 'd Ng 1776 El:

eet, N.W.

Suite h a Washington.. G.C.

20006 Joseph R. Egan, Esquire Shaw, Pittman, Potts 2 Trowbridge 2300 N Street, N.W.

Washington, D.C.

20037-1128 Mr. Regis A. Matzie, Vice President Nuclear Systems Developrent ABB-Combustion Engineering, Inc.

1000 Prospect hill Road Post Office Box 500 Windsor, Connecticut 06095-0500 Mr. Victor G. Snell, Di: ector Safety and Licensing W

AECL Technolodes 9210 Corporait Boulevard j

Suite 410 Rockville, Maryland 20850

..-- = -. :

CESSAR ninem:n sdw6 5RxES a

4 16.14 4.0 DESIGN FEATURES i

16.14.1 4.1 SITE pesign Festune 4.0 4.1 SITE 4.1.1 Site and Etelusion Ares Boundiries ne site and exclusion area boundaries (shall be as described or as shown in Figure 4.1 1].

4.1.2 Low Poeulation Zone (LPZ)

The LPZ (shall be as described or as shown in Figure 4.12].

4.2 REACTOR CORE 4.2.1 Fuel Assemblies f 4p4,. S. ' pall contain (241] fuel assemblies. Each assembly shall consist of a matrix of The res 6.n.y

...d fuel rods with an initial composition of natural or slightly enriched uranium ioxi e J as fuel material. Limited substitutions of zirconium alloy or stainless steel

• yAj filler rods for fuel rods, in accortlance with approved applications of fuel rod l

y configurations, may be used. Fuel assemblies shall be limited to those fuel designs that K

l have been analyzed with applicable NRC staff approved codes and methods and shown by o

tests or analyses to comply with all fuel safety design bases. A limited number oflead test assemblies that have not completed representative testing may be placed in nonlimiting core n

' dab regions.

4.2.2 fControl Rodl Assemblies The reactor core shall contain (921 control element assemblies (CEAs). The control material shall be (silver indium cadmium, boron carbide, or hafnium metal] as eg. proved by ithe NRC.

i k

I-SYSTEM 80+

4.0-1 l

Amendrnent K 16.14-1 October 30,1992 Enclosure

~..

CESSAR E!ainumn l

i 16.14.3 4.3 FUEL STORAGE Ocaign Features f

4.0

.w 4.3 FUEL STORAGE c'

4.3.1 Criticality K

4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

Fuel assemblies having a maximum U-235 enrichment of [5.0] weight a.

percent; b.

K,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in [Section 9.1 of the ]fSAR];

[c.

A nominal [9.78] inch center to center distance between ets;; x:';

-spkJ 4. a:l Ux's..' -

p.. S ?!". A.r m uy.b fuel assemblies placed in [the high density fuel storage racks];]

[d.

A nominal [9.78] inch center to center distance between av..e

l -

.~

y

, e. 7.,4 m;,k,-" 5?d...g deu iv m A SG -ge mig iur t

g. PVT fuel assemblies placed in [the low density fuel storage racks];]

I

[e.

New or partially spent fuel assemblies with a discharge burnup in the

" acceptable range

• of Figure [3.7.20-1] may be allowed unrestricted g g(vd storage in [either] fuel storage rack)(s); and]

1. V)

St o

4

[f.

New or partially spent fuel assemblies with 's discharge bumup in the "7

1. 1 Ab

" unacceptable ranae* of Figure [3.7.20-1] will be stored in compliance

[K5 R. approvKproqurgL QCobcp ifigon on with g

kc I

b 3

- - ' 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

I

^

Fuel assemblies having a maximum U-235 enrichment of [5.0] weight s

a.

percent; b.

K,, 50.95 if fully flooded with unborated water, which includes an allowance for ui.artainties as desenbed in [Section 9.1 of the XSAR];

K,,s0.90 if moderated by aqueous foam which includes an allowance for c.

i uncertainties as described in fection 9.1 of the M]; and

\\

sal.

l l

d.

A nominal [9.78] inch center to center distance between da ;

nu,,,t.a w;rh r,it Lt~ w g A,.,:m-e p,g m 50 :n ;;; z-_ q =

y l

fuel assemblies placed in the storage racks.

l i

SYSTEM 80+

4.0-4 i

Amendment K 16.14-4 October 30,1992

CESSARH % d JPcWw A RPa i

16.15.5 5.5 REVIEWS AND AUDITS

~

Reviews and Auosts W

5.5 5.5 REVIEWS AND AUDITS 4

42 o

- t TTe licen'see shall describe the method (s) established to conduct independent reviews and K

a audits. De methods may take a range of forms acceptable to the NRC. Dese rnethods 4 nclude creating an organizational unit or a standing or ad hoc committee, or assigning i

1. I individuals capable of conducting these reviews and audits. When an individual performs a review function, a cross disciplinary review determination is nea==y. If deerned neceuary, such revim shall be performed by the review personnel of the appropriate discipline. Individual reviewers shall not review their own work. Regardless of the method used, the licensee shall specify the functions. organi ati_onal arrangement, responsibilities, eppm.e='a ANSI /ANS-3-txt98Tiisilfications, and reporting requiremems of y.

3 I

(

functionapelement or unit that contributes to,[hese processes. 4 in i f=.t

N"-

e g ?- - a: __

?

p7

- m a, ; 4.q : h -2 ;;,..;, u : -

!%. = ^7

. /

e

-Reviews undTudiIrof sctivities arrecting plant sarety have two distinct elements. Ther5rn 6

element is the reviews performed by plant staff personnel to ensure that day to day activities are conducted in a safe manner. Besc reviews are described in Section 5.5.1. He second element, described in Section 5.5.2, is the [offsite] reviews and audits of unit activities and programs affecting nuclear safety that are performed independent of the plant staff. The loffsite] reviews and audits should provide integration of the stviews and audits into a

' cohesive program that provides senior level utility management with an assessment of facility operation and recommends actions to improve nuclear safety and plant reliability. It should include an assessment of the effectiveness of reviews conducted according to Section g.5.1.

5 5.5.1 E! ant Reviews I

' M.M 9

The licensee shall describe provisions for plant reviews (organization, reporting, records) and the appropnate ANSI /ANS standard for personnel qualification.

J 5.5.1.1 Functions

~

\\

The [ plant review method specified in Specification 5.5.1) shall, as a minimum, incorporate functions that:

a.

Advise the [ Plant Superintendent] on all matters reist to nuclear fetyt 4

Recommend to the [ Plant Superintendent] approval or disap/ oval of}tems b.

considered under Specifications 5.5.1.2.a through 5.l.2.$ prior to t eir implementation, except as provided in Specification

.l.3; (continued)

L SYSTEM 80+

5.0-10 Amendrnent K 16.15-10 October 30,1992

CESSARUSLma Revihws and Audits i

5.5 1

l 5.5.1.1 Functions (continued)

J I

Obd :pp;;;:! 6- 'k- ["k : Sy,..

L 1.viid. L.._,

s;;;;i:.; = "it :;;; "-d =^ : ;" ~*i= p; M,u,lu z n.v.;.,7 a

.,z. ;; ;;p;:!---..ma pmm.,ma,s...., --g. : 3y,;;;,;;,; ;c g;,

= q :y_; 2 ;..L; ; :':r de;i r a 0 -sk

-.. ~

jff.

Determine whether each item considered under Specifications 5.5.1.2.a through 5.5.1.2Mconstitutes an unreviewed safety question as defined in 10 CFR 50.59; and

)(d.

Notify the (Vice President - Nuclear Operations) of any safe'v significant disagreement between the { review organization or individual specified in Specification 5.5.1] and the [ Plant Superintendent) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

However, the [ Plant Superintendent) shall have responsibility for resolution of such disagreements pursuant to Specification 5.1.1.

5.5.1.2 Responsibilities The (plant review method specified in Specification 5.5.11 shall be used to conduct, as a minimum, reviews of the following:

a.

All proposed procedures required by Specification 5.7.1.1 and changes g

thereto; b.

All proposed programs required by Specification 5.7.2 and changes thereto; All proposed changes and modifications to unit systems or equi ment that c.

affect nuclear safety;

\\..

Q d.

All proposed tests and experiments that affect nuclear sa

M 7

Review -d dmmentationofjudgtfrent concerningpeRWgao.. - ::

• e.

wiiprot%: th ---4 p!rro '- byF.mr.c Grig-* -view-

,(

meetzng}4ad the-sepair-of sha-eb r:!p., d All proposed changes to these Technical Specifications (Th. their Banes.

6-. k and the Operating 1.icense.

4 (continued)

I y

2 SYSTEM 80+

5.0-11 Amendment K 16.15 11 October 30,1992

~ ~

~ ~

~~'~~

CESSAR Enn"icni:n l

1 Reviews and Audits 5.5 j

5.5.3 Records (continued)

Ji I

s.

b.

Recommendations to the management of the organization being audited; An assessment of the safety sigm6cance of the review or audit findings;

{

c.

d.

Recommended approv orfik royal of items considered under Specifications 5.5.1.2.s through 5. 1.2/; anc.

e.

D ermirui. whether ese em considered under Specifications 5.5.1.2.a through e.

5..l.2.(

titutes an unreviewed safety question as defined in 10 CFR 50.59.

d.

W 1

K 1

l

\\ :.

e SYSTEM 80+

5.0-15 Amendment K 16.15-15 October 30,1992

CESSARHa% -

1 1

Procedures, Programs, and Manuals 5.1

\\

i j

n 5.7.2.2 Proc:ss Control Program (PCP)(continued)

,j Licensee initiated changes to the PCP:

Shall be documented and records of reviews performed shall be retained.

a.

This documentation shall contain:

1.

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

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

b.

Shall be effective after review and acceptance by the [ review method of Specincation 5.5.1] and the approval of the [ Plant Superintendent].

5.7.2.3 Offsite Dose Calculation Manual (ODCM)

The ODCM shall contain the methodology and parameters used in the a.

calculation of off;ite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent moaitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program:

K b.

The ODCM shall also contain the Radioactive Effluent Controls and Radiological Environmental Monitoring programs required by Specification 0'f' 5.1.2, and descriptions of the infortnation that shoul uded in t pt Annual Radiological Environmental Operating, snuannua Radioactive Effluent Release Reports required by Specification [5.9.1.3] ]

g'3 u

and Specification [5.9.1.4j.

j$}

Licensee initiated changes to the ODCM:

08 PSt h f,0.3, Shall be documented and records of reviews performed shall be retain $.

s.

This documentation shall contain:

1.

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

(continued) 7 i

SYSTEM 80+

5.0-19

\\

Amendment K 16.15-19 October 30,1992

~~

CESSARMa h nt Procedures Programsfand Manuals

.L 5,7

,4 5.7.2.3 Offsite Dose Calculation Manual (ODCM)(continued) p,,,y4, 2.

A determination that the change (s) ma' tain the levels of M

_j radioactive effluent control requi 10 CFR 20.nN",40 CFR 190,10 CFR 50.36a, and 10 CFR 50, Appendia 1, and not adversely impact the accuracy or reliability of effluent, dose, or i

setpoint calculations.

b.

Shall become effective after review and acceptance by the [ review method of Specification 5.5.l] and the appmval of the [ Plant Superintendent),

c.

Shall be submitted to the NRC in the form of a complete, legible cop of Radioactive Effluent Release Report for the period o..g-M;C

- pdp the entire ODCM as a part of or concurrent with th mianT ~

any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.7.2.4 Primary Coolant Sources Outside Containment His program provides controls to minimize leakage from those portions of systema outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. De systems include [the law K

Pressure Core Spray, High Pressure Core Spray, Residual Heat Removal, Reactor Core Isolation Cooling, hydrogen recombiner, process sampling, and Standby Gas Treatment). The program shallinclude the following:

a.

Preventive maintenance and periodic visualinspection requirements; and h

b.

Integrated leak test requirements for each system at refueling cycle intervals or less.

5.7.2.5 in Plant Radiation Monitoring his program provides controls to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. His program shallinclude the following:

a.

Training of personnel; g

i. (continued) y SYSTEM 80+

5.0-20 Amendment K 16.15-20 October 30,1992

CESSAR !!ninema I

y Procedures. Programa, and Manuals y

5.7 3

gp 5.7.2.3 Offsite Dose Calculation Manual (ODCM)(continued) g A

2.

A determination that the change (s) tain the levels of, OD radioactive effluent control requi 10 CFR 20.#,40 CFR 190,10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

1 b.

Shall become ef)ective after review and arrear

• by the [ review method of Specification 5.5.1] and the approval of the (Plant Superintendent),

Shall be submitted to the NRC in the form of a complete, legible copy of c.

the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the arts of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

PIN NEd hM 8

^5 wno co/

N=.

5.7.2.4 Primary Coolant Sources Outside Containment h @/ g, g,g g g

corr +ckA de, hM Syr,%90 4'9hc.

This program providea controls to minimir.e leakage from those portions of systema outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include [the44wn K

--fressure Core SpreyrHigh Pressure Core Spray, Residual Heat Removal,. Reactor.

g~ t Core isolation Cooling. hydrogen recombmerQtc5Es sampling, ana tr-%y n*=

m

~

py

-- Tg The program shall include the following:

eq f)g &l s'

Preventive maintenance and periodic visual inspection requirements; and 1

Q a.

b.

Integrated leak test requirements for each system at refueling cycle j

W intervals or less.

5.7.2.5 In Plant Radiation Monitoring This program provides controls to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shallinclude the following:

a.

Training of personnel; (continued) ~_

SYSTEM 80+

5.0-20 Amendment K 16.15-20 October 30,1992

.ESSAR 880icam,.

SeebeSh GRc6

't Procedures Programs, and Manuals 5.1 5.7.2.5 in Plant Radiation Monitonng (continued) l i

b.

Procedures for monitoring; and c.

Provisions for maintenance of sampling and analysis equipment.

5.7.2.6 Post Accident Sampling his program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.The pro ram shall

'ib a c% ng e ia c.o # {-orm aw ca. w ip,)

include the following:

Jo,3 not 4me to oF R 5'o.14(O(.t)@ m ggg

>g Training of personnel; a.

14%uk 3 GouQ L skcLuicd.

b.

Procedures for sampling and analysis; and c.

Provisions for maintenance of sampling and analysis equipment.

5.7.2.7 Radicactive Effluent Controls Program g

This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The programs shall be contained in the ODCM, shall be implemented by operating procedures, and shall include remedial actions to be taken whenever the program limits are exceeded, ne program shall include the following elements:

Limitations on the functional capability of radioactive liquid and ganous a.

monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

/*Joh.>44.casI JnL' v1 Limitations on the concentrations of radioactg materia 19ea*,sednt oO i

to liquid b.

effluents to unrestricted areas, conforming to M CTR 20, Appendix B.

Table, Column 25 to e o CPR. 2o. ice 1 - 2o, Mo,,

I3 an-c.

Monitoring, sampling, and analysis of radio tive liquid and gaseous effluents.ic re;d_.x -ii 10 CFR 20.

and with the methodology and parameters in the ODCM; (

ysesa. A %

(continued)

SYSTEM 80+

5.0-21 j

Amendment K 16.15-21 October 30,1992

--.mw---.%

CESSAR 8Hnneme,.

b.

Favvtetone for safety-related anubbers in accordance with 10 CTR i

a 50.S$e. Safety related enubbers included thoes installed on i

enfaty-related componente and those instelled on noneefety related componente !! their f ailure or f ailure of t.he component on which j

they are Anetelled would have en adverse effect on any eefetyj reisted systee.

Procedures, Progra@sps, and Manuals

. A-5.7 l

ti 4

l I( 5.7.2.)C Inservice Testing Program (continued) i s>

qg Testing frequencies specified in Section XI of.the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice testing performing inservice testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least race per 276 days j

l Yearly or annually At least <suce per 366 days g

Biennially or every 2 years At least once per 731 days Q

The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; Q.

7te provisions of SR 3.0.3 are applicable to inservice testing activities; and

\\.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

.D 5.7./. )s t, 4St m Generator (SG) Tube Surveillance b g.,, g y%

y. pengnm -!(e:: =t# rm -,-+; sc :a a,. d.;,

. g., a Su a.:ita.4,.

^ " be d-~~'

'M OPEP)."LC L,,o sms &c mummm of @;f.=as

-5 '.2.:::.;d $ a pp a w r;;--'M !=:H:: L :pe::!:: p;;;;= 1:: L.:!r' :

3

' !.= i; f;!!:uing:

_ m e mpt, ot-,:~. --g : 7,:~,.

h_

$O erb; -

fa emletinn and intrw finn-(continued)

SYSTEM 80+

5.0-25 Amendment K 16.15-25 October 30,1992

CESSAR Enfinemn i

-Y Procedures, Programs and Manuals 5.7 c,

4d 4

j 9 d in tf-5.7 S m Generator (SG) Tube Surveillance (continued)

W n._._-__a,..__-...2e.v....w.~r..,.___... -

-d.

^ =:p:.: n.. a....

d n.: u :...;.i 1:q::::y ;f.ap:.

e.

lK:y :':re - :: k e.v..JJ.;-

IS 5.7.2.M Secondary Water Chemistry This p ogram provides controls for monitorbg secondary water chemistry to iniu%t SG tube degradation sad low pressure turoce disc stress corrosion cracking.a.The program shall include:

a.

Identification of a sampling schedule for the critical variables and control points for these variables; b.

Identification of the procedures used to measure the values of the critical variables; E

Identification of process sampling points which shall include monitoring c.

the discharge of the condensate pumps for evidence of condenser in leakage; d.

Procedures for the recording and management of data; Procedures defining corrective actions for all off control point chemistry e.

g..

conditions; and f.

A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.7.2.

Ventilation Filter Testing Program hp rp

1. prap.

,L

6 cabiisoco to impiemw. ;1.; f:!!:ut;.y..J :_::!:; ef fHterr n aaoraance wna iT ;9'~v n" A LS2, ?: +- 2, ::.".M:: N:;0 t99M-

+

kkdd d

f (cont nued) 1 SYSTEM 80+

5.0-26 Amendmr.-t P:

16.15-26 October 30,1992

CESSAR innncamw r

Procedures, Programpand Manuals T

5.7 F

w 5.7.2JT Diesel Fuel Oil Testing Program k

A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:

a.

Acceptability of new fuel oil for use prior to addition to storage tanks by detemuning that the fuel oil has:

1.

An API gravity or an absolute specific gravity within limits:

2.

A flash point and kinematic viscosity within limits for ASTM 2D fuel oil; 3.

A clear and bright appearance with proper color, b.

Other properties for ASTM 2D fuel oil are within

'ts within 30 days following sampling and addition to storage Th c to-n 4 d, y Total particulate concentration of the fuel oil 's :.L../1,f1o mg ;

chen tested 4gg g

c.

.T Qn y ga y

every 31 days in accordance with ASTM D-6, Method A-A 3.

g W GTs, 1

M"O 5 7.3.17 4

fr.hfie 2<.) w.~

s d

hw e r. w k a u W gs %(

4 This program provides controls to ensure that appropriate fire b Ng"*

M #M-protection measures are maintained to protect the plant from fire and to ensure the capability to achieve and maintain safe shutdown In the event of a fire is maintained.

p SYSTEM 80+

5.0-28 Amendment K 16.15-28 October 30,1992

1. 49% em yse*'

44W sJ.re s, "Agihe a N. mare 46 gurJune CESSARiEfinc =

k Reportingitequirements 5.9 f{0 y

5.9.1.3 Annual Radiological Environmental Operating Report (continued) p0 ne Annual Radiological Environmental Operating Report c v ration of h'

the unit during the previous calendar year shall be submit by y 15 o "esch 1

year. The report shall include summaries, interpretations, ariJ trends of the results of the Radiological Environmental Monitoring Program reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix 1, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations speci6ed in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1. November 1979. [ne report sball identify the thermolumincscent dosimeter (TLD) results that repreacnt collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.] In the event that some individual sesults are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be suh s in a supplementary report as soon as possible.

5.9.1.4 Lw! Radioactive Effluent Release Report j

e 7

e h fr.an e l-b

-NOTE A single submittal may be made for a multiple unit station bmna j

j combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive matenal from each unit.

N civo l*

4%. pvn yn,.

~

~

The Sn:2-".1 adioactive Efiluent Release Report covering the ope e_

g gg unit dW 'h,=!c= 5 rer'h: ef e,- r'!:: shall be submitted :.. _ cy

~ ~

d.r '

7 ! rd h?y ' cf ni ;=. The report shallinclude a summary of e quantities of radioactive liquid and gaseous effluents and solid waste released from f

the unit. Tbc material provided shall be consistent with the objectives outlined in

/

the ODMC and Process Control Program (PCP) and in conformance with 10 CFR 50.36: and 10 CFR 50. Appendix 1.Section IV.B.I.

p (continued)

}, o s- % nyI?aAexk 1e 2 y G e.a.as m <$r A w C M 51 4 SYSTEM 80+

5.0-33 Amendment K 16.15-33 October 30,1992

w L'

CESSARin h a fem 6el 6

Reponing Requi,rements

.d S.9 S.9.1.7 RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)(continued) temperature limits including the bestup and cooldown rates shall be those previously reviewed and approved by the NRC in (Topical Repon(s), number, title, date, and NRC staff approval document, or staff safety evaluation repon for a plant specific methodology by NRC letter and datej. Tbc reactor vessel pressure and temperature limits, including those for bestup and cooldown rates, shall be deternuned so that all applicable limits (e.g., beatup end limits, cooldown limits, and inservice leak and hydrostatic testing limits) of the analysis are met. The PTLR, including ruisions or supplements thereto, shall be provided upon issuance for each reactor vessel fluency period.

S.9.2 Special Reports

(~~~Special Reports may be required covering inspection, test, and maintenance activities, j

These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

]

Special Repons shall be submitted in accordance with 10 CFR S0.4 within the time period i

specified for each report.

The following Special Repons shall be submitted:

g In the event an ECCS is actuated and injects water into the RCS in MODE 1,0c 2,v 3 a.

j a Special Repon shall be prepared and submitted within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nor.zle shall be provided in this Special Repon whenever its value exceeds 0.70; s

N

)

b.

indtvidual emergency diesel generator (EDG) experiences 4-or niiirelslid s..

failures i ast-25 demands, these failuresAvalid failures l

experienced by that

~]

'55d shall be reported within 30 days.

Repons on EDG failurcs-include the in mmended in Regulatory,

i i

Guide,1.9Avistoii3, Regulatory Position C.S. o'r'iiXistia e

Guide reporting requirement; and N

+

/

\\

continued) l 1(M N

l c@n/d M'

xdad 5

SYSTEM 80+

S.O $5 Amendroent K 16.15-35 October 30,1992

CESSAR HM,icma -

Reponing Requirements 5.9 5.9.2 Special Reports (continued)

When a Special Repon is required by Condition B or F of LCO 3.3.(X]? a repon c.

shall be submitted within 14 days.f.a i; :'n 1: : 6. is i+;;.d. The repon stall outline the preplanned alternate method of monitoring,the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to OPERABLE status, cl.

e.

b d

g,.g i u e) s b be-P co d'd hr E M C.i5 Wid g

i d.

Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall L_

include a description of the tendon condition, the condition i

of the concrete (especially at tendon anchorages), the j

inspection procedures, the tolerances on cracking, and the l

corrective action taken.

e.

Followingeachinserviceinspectionofsteamgenerator(SG)~

tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days.

s g

. q-5 I'

SYSTEM 80+

5.0 36 Amendment K 16.15-36 October 30,1992 I

l j