ML20064C642

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Proposed Tech Specs,Incorporating Current Provisions of 10CFR50.36(a)2 Re Semiannual Radioactive Effluent Release Rept to Be Submitted Annually Rather That Semiannually
ML20064C642
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/25/1994
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20064C633 List:
References
NUDOCS 9403100145
Download: ML20064C642 (42)
v • d • e


Text

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! 0FFSITE DOSE CALCULA1 ION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology

' and parameters used in the calculation of offsite doses resulting from  ;

radioactive gaseous and liquid effluents, in the calculation of gaseous and l liquid effluenti monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiologica.1 Monitoring Program. The ODCM shall also contain l (1) the Radioactive Effluent Controls and Radiological Environmental  !

! Monitoring Programs required by Section 6.8.4 and (2) descriptions of the i information th tgpgtd-bg i included in the Annual Radiological Environmental ,

i Operating and maannuSRadioactive Effident Release Reports required by i Specifications b. . . and 6.9.1.8.  !

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l OPERABLE - OPERABILITY -

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1.18 A system, subsystem, train, component or device shall be OPERABLE or l have OPERABILITY when it is capable of. performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power,

' cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capaole of performing their related support function (s).

] OPERATIONAL MODE - MODE a

1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive 4

combination of ccre reactivity condition, power level and average reactor coolant temperature specified in Table 1.1 1

PHYSICS TESTS 4

1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental i- nuclear characteristics of the reactor core and related instrumentation and i 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions i of 10 CFR 50.59, or 3) otherwise approved by the Commission.

4 PRESSURE B0UNDARY LEAKAGE i

i 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube

, leakage) throuch a non-isoiable fault in a Reactor Coolant System component

body, pipe wall or vessel wall.

PROCESS CONTROL PROGRAM (PCP) l 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, a sampling, analyses, tests, and determinations to be made to ensure that

processing and packaging of solid radioactive wastes based on demonstrated

~ processing of actual or simulated wet solid wastes will be accomolished in such a way as to assure compliance with 10 CFR Parts 20, 61, and'71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

, PURGE - PURGING 1.23 PURGE or PURGING is the contro' led process of discharging air or gas 4

I from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

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SUMMER - UNIT 1 1-4 Amenoment No. 104 1

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

i DEFINITIONS _ l i 0FFSITE DOSE CALCULATION MANUAL (0DCM) 1.17 The GFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and i i liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the l Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by [ l Specifications 6.9.1.6 and 6.9.1.8. I i

OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or

have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.19 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.

PHYSICS TESTS 1.20 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes wil be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

SUMMER - UNIT 1 1-4 Amendment No. 104

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~D eLi n iri an S fildOWER TILT RATIO i

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.z4 ydADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore )

detector calibrated output to the average of the upper excore detector cali- )

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brated outputs, or the ratio of the maximum lower excore detector calibrated I output to the average of the lower excore detector calibrated outputs, whichever

, is greater. With one excore detector inoperable, the remaining three detectors i

shall be used for computing the average.

RATED THERMAL POWER -

! ^

! 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to l the reactor coolant of 2775 MWt. _

REACTOR TRIP SYSTEM RESPONSE TIME l

1 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

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REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHUTOOWN MARGIN 1.28 SHUT 00WN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present conditio1 assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivi y worth which is assumed to be fully withdrawn.

SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shall be the energization of eacn slave relay and verification of OPERABILITY of eacn relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.

1.30 Not Used SOURCE CHECK

1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

I SUMMER - UNIT 1 1-5 Amendment No. 35,104

l DEFINITIONS l

PURGE - PURGING l 1.23 PURGE or PURGING is the controlled process of discharging air or gas i from a confinement to maintain temperature, pressure, humidity, concentration
or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

l l OUADRANT POWER TILT RATIO

1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore 2

detector calibrated output to the average of the upper excore detector cali-l brated outputs, or the ratio of the maximum lower excore detector calibrated

, output to the average of the lower excore detector calibrated outputs, whichever

i. is greater. With one excore detector inoperable, the remaining three detectors i shall be used for computing the average.

RATED THERMAL POWER

] 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to

the reactor coolant of 2775 MWt.

l REACTOR TRIP SYSTEM RESPONSE TIME i

1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.  !

i REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

I SHUTDOWN MARGIN

! 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which

' the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of hghest reactivity worth which is assumed to be fully withdrawn.

SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include j a continuity check, as a minimum, of associated testable actuation devices.

1.30 Not Used j SOURCE CHECK i-1 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

SUMMER - UNIT 1 1-5 Amendment No. 35, 104

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TABLE 3.3-4 (Continued) 3 .

ENGINEERED SAFETY' FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS .

g Total q Functional Unit ,

Allowance (TA) *Z S_ Trip Setpoint Allowabic Value

3. CONTAINMENT ISOLATION
a. , Phase "A" Isolation
1. Manual NA NA NA NA NA
2. Safety Injection See 1 above for pil safety injection setpoints and allowable values
3. Automatic Actuation Logic NA NA NA NA -

NA and Actuation Relays

.b. Phase "B" Isolation -

1. Automatic Actuation HA NA- NA NA NA

$ Logic and Actuation

, Relays -

$ 2. Reactor Building 3.0 0.71 1.5 112.05 psig 112.31 psig Pressure-High 3 -

c. Purge and Exhaust Isolation
1. Safety Injection See 1 above for all safety injection setpoints and allowable values
2. Containment Radioactivity NA NA NA *
  • High
3. Automatic Actuation HA NA NA NA . Nk
. '$" Logic and Actuation .

[ Relays a

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  • Trip setpoints shall be set to ensure that the limits o pecification ,L41 M re t~cx ded.

CYDCm Spec.rA 4-icn 1.1.l. ,

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E TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Q Total

__ Functional Unit Allowance (TA) Z S Trio Setpoint Allowable Value

3. CONTAINMENT ISOLATION
a. Phase "A" Isolation
1. Manual NA NA NA NA NA
2. Safety Injection See 1 above for all safety injection setpoints and allowable values
3. Automatic Actuation Logic NA NA NA NA NA ti e

and Actuation Relays

{w b. Phase "B" Isolation

1. Automatic Actuation NA NA NA NA NA Logic and Actuation Relays
2. Reactor Building 3.0 0.71 1.5 512.05 psig 512.31 psig Pressure-High 3
c. Purge and Exhaust Isolation

! 1. Safety Injection See 1 above for all safety injection setpoints and allowable values

2. Containment Radioactivity NA NA NA * *
y High i

s g- 3. Automatic Actuation NA NA NA NA NA g Logic and Actuation

Relays w

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  • Trip setpoints shall be set to ensure that the limits of ODCM Specification 1.2.2.1 are not exceeded.

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INSTRUMENTATION TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS t

e. Reactor Building Purge and Not Applicable Exhaust Isolation Emergency Feedwater Pumps f.
g. Service Water System McA(e

.f.71.5(4)/81.5(5)

h. Reactor Building Cooling Units s 76.5(4)/86.5(5)
i. Control Room Isolation Not Applicable l
3. Pressurizer Pressure-Low
a. Safety Injection (ECCS) 527.0(2)/27.0(1) i
b. Reactor Trip (from SI) 53.0
c. Feedwater Isolation $10.0
d. Containment Isolation -Phase "A" $45.0(4)/55.0(5)
e. Reactor Building Purge and Not Applicable Exhaust Isolation
f. Emergency feedwater Pumos tJpp)4c
g. Service Water System 6 71.5(4)/81.5(5)
h. Reactor Building Cooling Units 6 76.5(4)f86.5(5) 4
i. Control Room Isolation Not Applicable
4. Differential Pressure Between Stean lines-Hioh l

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a. Safety Injection (ECCS) 527.0(2)/37.0(3)
b. Reactor Trip (from SI) 13.0
c. Feedwater Isolation $10.0
d. Containment Isolation -Phase "A" $45.0(4)/55.0(5)

SUMMER - UNIT 1 3/4 3-30 Amendment No. 57, 108 l

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! INSTRUMENTATION TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

e. Reactor Building Purge and Not Applicable l Exhaust Isolation
f. Emergency Feedwater Pumps Not Applicable  ;
g. Service Water System $71.5(4)/81.5(5) l
h. Reactor Building Cooling Units $76.5(4)/86.5(5) l
1. Control Room Isolation Not Applicable

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3. Pressurizer Pressure-Low I
a. Safety Injection (ECCS) 527.0(2)/27.0(1)
b. Reactor Trip (from SI) 53.0
c. Feedwater Isolation $10.0
d. Containment Isolation -Phase "A" $45.0(4)/55.0(5)
e. Reactor Building Purge and Not Applicable Exhaust Isolation
f. Emergency Feedwater Pumps Not Applicable i

i g. Service Water System 571.5(4)/81.5(5)

h. Reactor Building Cooling Units $76.5(4)/86.5(5)
1. Control Room Isolation Not Applicable
4. Differential Pressure Between Steam Lines-Hiah
a. Safety Injection (ECCS) 527.0(2)/37.0(3)
b. Reactor Trip (from SI) 53.0
c. Feedwater Isolation $10.0
d. Containment Isolation -Phase "A" $45.0(4)/55.0(5) l i

SUMMER - UNIT 1 3/4 3-30 Amendment No. 67, 108

4 INSTRUMENTATION 4

TABLE 3.3-5 (Continuec)

TABLE NOTATION 1

, (1) Diesel generator starting and sequence loading delays from under 4

voltage included. Response time limit includes pos,itioning of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps and RHR pumps. Sequential transfer of '

centrifugal charging pump suction from the VCT to the RWST (RWST l valves open, then VCT valves close) is not included.

(2) Diesel generator starting delay n included. Sequence loading delay l includea. Offsite power availab e. Response time limit includes positioning of valves to establish 51 path ano attainment of '

, discharge pressure for centrifugal charging pumps. Secuential i

transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

(3) Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included. ,

1 (4) Diesel generator starting delay not included. Sequence loading delay included. Offsite power available.

(5) Diesel generator starting and secuence loading delays from undervoltage included.

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SUMMER - UNIT 1 3/4 3-34 Amendment No.108

INSTRUMENTATION TABLE 3.3-5 (Continued) l TABLE NOTATION  !

(1) Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves to establish SI path and attainment of discharge pressure for l centrifugal charging pumps and RHR pumps. Sequential transfer of l centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is not included.

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(2) Diesel generator starting delay not included. Sequence loading delay l included. Offsite power available. Response time limit includes positioning of valves to establish SI path and attainment of l

discharge pressure for centrifugal charging pumps. Sequential transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then VCT valves close) is included.

(3) Diesel generator starting and sequence loading delays from under voltage included. Response time limit includes positioning of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. Sequential transfer of centrifugal charging pump suction from the VCT to the RWST (RWST valves open, then the VCT valves close) is included.

(4) Diesel generator starting delay not included. Sequence loading delay

, included. Offsite power available.

(5) Diesel generator starting and sequence loading delays from undervoltage included.

SUMMER - UNIT 1 3/4 3-34 Amendment No. 108

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! INSTRUMENTATION h l

l EXPLOSIVE GAS MONITORING INSTRUMENTATION l

' LIMITING CONDITION FOR OPERATION 1

3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table  !

3.3-13 shall be OPERABLE wit hJ 1armLtrjp_setpqint tr et A e e that

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pedfin 3. .2. are . The-ahr#/-trap  !

I l +etpoints of thaca hane!s chall be deteriiiiiied in acc;rd: ce "ith the nncu l g APPLICABILITY: As shown in Table 3.3-13 ACTION:

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i a.

1 With a explosive gas monitoring instrumentation channel alarm / trip l j

setpoint less conservative than required the above Specification, declare the cnannel inoperaole, and tak A ION shown in Table l 3.3-13. +n l '

I b.

' With less than the minimum number of explosive gas effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to operable i i t

status wi thin 30 days and, if unsuccessful prepare and submit a l Special Report to the Commission pursuant to specification 6.9.2 to puhrWNy'thTT~itoperaal Tity-was7et-cerrec4edvin-adim manner.

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Addi13-11y H +his condit;cn prevaih for mer: than 30 day:, .n-1 the next seriannual ef'htnt repert, exp hin why thi: noperability i u=s not corrected ia e timely manncr.-

c. The provisions of Specification -0.C.1.db,3.0.3and3.0.4arenot i applicable.

j SURVEILLANCE REQUIREMENTS 4

4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, 500l1C CliECK, i

CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the l frequencies shown in Table 4.3-9.

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i SUMMER - UNIT 1 3/4 3-67 Amendment No. 35, 104

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INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION l 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded. l APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With an explosive gas monitoring instrumentation channel alarm / trip l setpoint less conservative than required by the above Specification, declare the channel inoperable end take the ACTION shown in Table l 3.3-13.
b. With less than the minimum number of explosive gas monitoring l instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to operable status within 30 days and, if unsuccessful prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.
c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION l and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.

SUMMER - UNIT 1 3/4 3-67 Amendment No. 35, 104

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SUMMER - UNIT 1 3/4 3-70 Amencment No. 20,104

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EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL MODES IN WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED

1. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM
a. Hydrogen Monitor **

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ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEGl FUNCTi]N 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design ano operating experience iaformation, including plants of similar design, wnich may indicate areas for improving plant safety.

CCMPOSITION 6.2.3.2 The ISEG shall be composea of a multi-disciplined dedicated onsite group with a minimum assigned complement of five engineers or appropriate specialists.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant activities to provide incecenaent verification

  • that these activities are performed correctly and that human errors are reduced as much as practical.

1 AUTHORITY 6.2.3.4 The ISEG shall make detailed recorsnendations for procedure revisions, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to the General Manager, 1 Nuclear Safety. i 6.2.4 SHIFT TECHNICAL ADVISOR The Shift Tecnnical Advisor snall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

6.3 UNIT STAFF OUALIFICATIONS l

6.3.1 Each memoe of the u staff shall meet or exceed the minimum uttTTTha n f AN 8.1-197PfUrNempefable 0051 tic s

uppi;;;=21 e?_'4-: :'ts sreci"ed dr Sati:= ^ ead r'a En:10:;r: 1 Of the

":r: . M, '^G^ ieu.=> 10 :!' licac.;ee; &; ;1erified da WoEG-0737, S:: tion j

' crijoMor'

!_nal, except for tne A;;;;i:te ":r;;r, M::!th "Wsics who shall meet or

'ProitCHOn exceed the qualifications of Regulatory Guide 1.8, September 1975, tM St.ift l MOJMc R chnic;l c--*d-- o

Advi nr who ,hel' :xt er ax;;;; tr.2 w eilih.aiivm , ci.. . ee te4-

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f er +k- nn ah-- m um "a" ' - +n alt 17Q7R,7;" C,']"*=.t- ~ a  ; tem .dbr ety  ;

Eng neering Group, each o w om shall have a Bachelor of Science degree or registered Professional Engineer and at least two years experience in their  !

l _d . At leaspuqear exoerienc Mn_ thy-racle r field. i 6.4 TRAINING g cg. gd retraining and replacement training program for the non-1 staff shal and shall meet or excee ements and hg4 recommendations of Section .. .- 1. Also, a retraining and replacement trai . or the license hall be maintained and-shetr Teet sr exceed the requirements of 10CFR55.59(c) an . .

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  • Not responsible for sign-off function.

SUMMER - UNIT 1 6-3 AMENOMENT NO. f8. 53 d , 106

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ADMINISTRATIVE CONTROLS i 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION

! 6.2.3.1 The ISEG shall function to examine plant operating characteristics,  ;

NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety. l

! COMPOSITION ,

6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated onsite I group with a minimum assigned complement of five engineers or appropriate l specialists. '

RESPONSIBILITIES 1 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of plant i activities to provide independent verification

  • that these activities are l performed correctly and that human errors are reduced as much as practical.

AUTHORITY l 6.2.3.4 The ISEG shall make detailed recommendations for procedure j revisions, equipment modifications, maintenance activities, operations J activities or other means of improving plant safety to the General Manager, l Nuclear Safety.

6.2.4 SHIFT TECHNICAL ADVISOR  ;

The Shift Technical Advisor shall provide technical support to the Shift 1 Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

6.3 UNIT STAFF QUALIFICATIONS

! 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Radiation Protection Manager who shall meet or exceed the qualifications of

! Regulatory Guide 1.8, September 1975, and the members of the Independent Safety l Engineering Group, each of whom shall have a Bachelor of Science degree or l

registered Professional Engineer and at least two years experience in their field. At least one year experience shall be in the nuclear field.

i 6.4 NOT USED l

l *Not responsible for sign-off function.

l SUMMER - UNIT 1 6-3 Amendment No. 18, 58 79, 106

I ,

ADMINISTRATIVE CONTROLS

. RECORDS i

6. E .1. 8 The Plant Safety Review Committee shall maintain written minutes of I i

eaca PSRC meeting that, at a minimum, document the results of all PSRC activ-ities performed technical under the responsibility and authority provisions of these specifications. Copies shall be provided to the Vice President Nuclear Operations and the Chairman of the Nuclear Safety Review Committee.

6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)

FUNCTION 6.5.2.1 The Nuclear Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of: ,

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a. nuclear power plant operations l
b.  !

nuclear engineering

c. themistry and radiochemistry
d. metallurgy
e. l instrumentation and control
f. radiological safety i g.

mechanical and electrical engineering

h. quality assurance practices l l COMPOSITION I l l 6.5.2.2 NSRC s cinted by the 14-censt-of7.CMar.d 4a + 4 " ^ "#-- " - " " - - Tuurw4ra-ether--membera

^^^-+i^~-

Vice Presiden , uc Ea in rane"""+4an ui+

o bioDhAn Yiiilli5NNe' members the NSRC shall have line responsibility for the operation of the unit.

The NSRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h. i ALTERNATES

. 5r2S v<re o erid All 4 ternate-eembar4JulLha--appog1Mewriting by the Exccutive ,

07dfEdo'ns;ent %VR geer 3tien, in c;r q tatier 'ith +6Vice President, t uc ear members in NSRC activities at any one time.

woalteTn'ateMhallparticipateasvoting CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to l provide expert advice to the NSRC.

SUMMER - UNIT 1 6-6 Amendment No. 7B, 73

i ADMINISTRATIVE CONTROLS RECORDS l 6.5.1.8 The Plant Safety Review Committee shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activ-ities performed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the Vice President, Nuclear Operations, and the Chairman of the Nuclear Safety Review Committee.

1 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)

FUNCTION  ;

I 6.5.2.1 The Nuclear Safety Review Committee shall function to provide l independent review and audit of designated activities in the areas of:

a. nuclear power plant operations I
b. nuclear engineering
c. chemistry and radiochemsitry j
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance practices COMPOSITION l

6.5.2.2 NSRC shall consist of a Chairman and four or more other members appointed by the Vice President, Nuclear Operations. No more than a minority l of the members of the NSRC shall have line responsibility for the operation of the unit.

The NSRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical l experience of which a minimum of three years shall be in one or more of the i disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.

ALTERNATES 1

6.5.2.3 All alternate members shall be appointed in writing by the Vice President, l Nuclear Operations; however, no more than two alternates shall participate as voting members in NSRC activities at any one time.

CONSULTANTS l

1 l 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advice to the NSRC.

l SUMMER - UNIT 1 6-6 Amendment No. 18, 79 l

1 I -

ADMINISTRATIVE CONTROLS l

l l

AUDITS J

6.5.2.8 The NSRC shall have cognizance of the audits listed below. Audits may

! be performed by using established SCE&G groups such as the ISEG and QA or by-outside groups as determined by the NSRC. Audit reports or summaries will be {

the basis for NSRC action:

a.

The conformance of unit operation to provisions contained

  • e 1

i tions and applicable license conditions at least nara na" " -aa+hs

b. The pe staff at least Wrainino cacc per--12 anMualifications ment @ of the entire unit c.

The results of actions unit equipment, struct taken to correct deficiencies occurring in ems or method f operation that affect nuclear safety at le::t enca nar maaths.

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

( AS&qr_ AIL.ceJIggram mm. _u .tn e criteria of Appendix "B", 10 CFR 50,

., a

,+u,. i

_u.

I e.

g ncy Plan and implementing procedures { eg t g m . , ~ . , . . . .

f. .ty Plan and implementing procedures m I

l

g. yerareacLantnparati nsidered appropriate by the NSRC, ycqtrze vice D*esident, Op- - +4-a or the Vice President, Nuclear Opera 1on . l
h. 'o Program and implementing procedures at ! east ence pe"_2M 3cnthn ( {
i. j An independent fire protection and loss prevention inspection and  !

audit shall be performed annually utilizing either qualified offsite licensee personnel or a qualified outside firm.

j. An inspection and audit of the fire protection and loss prevention l

program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

k.

The radiological environmental monitoring program and the results thereof, including the performance of activities required by th

'ty~ assure len t once per 12 months.m per R.G. 4.15 Rev. 1, February 1979, l

1. EMF 4UEJOSE Al lent c,.s pc. 24 months LATION MANUAL and implementing procedure h l m.

The PROCESS CONTROL PROGRAM and implem3nting arg edute solidification of radioactive wastes 't le::t enra per 2A monthL l

l AUTHORITY V

._2.9_ The NSRC shall report to and advise the secut.ive Vice Presi e ntCA eni- M perations on those areas of responsibility speci j in Sect. ions . . 2. and SUMMER - UNIT 1 6-8 Amendment No. M ,/7,79 -l

ADMINISTRATIVE CONTROLS l

AUDITS 6.5.2.8 The NSRC shall have cognizance of the audits listed below. Audits may be performed by using established SCE&G groups such as the ISEG and QA or by I outside groups as determined by the NSRC. Audit reports or summaries will be ,

the basis for NSRC action: l

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions. l l
b. The performance, training and qualifications of the entire unit l staff. l !
c. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety. l l
d. The performance of activities required by the Operational Quality I Assurance Program to meet the criteria of Appendix "B", 10 CFR 50. l 1
e. The Emergency Plan and implementing procedures.

l

f. The Security Plan and implementing procedures. l l l
g. Any other area of unit operation considered appropriate by the NSRC I or the Vice President, Nuclear Operations. l I
h. The Fire Protection Program and implementing procedures. l
i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or a qualified outside firm.
j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

l k. The radiological environmental monitoring program and the results j

thereof, including the performance of activities required by the quality assurance program per R.G. 4.15 Rev. 1 February 1979. l

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures. l
m. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes. l AUTHORITY 6.5.2.9 The NSRC shall report to and advise the Vice President, Nuclear l Operations, on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

SUMMER - UNIT 1 6-8 Amendment No. 16, 72, 79

l ,

a ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 as indicated below: Records of NSRC activities shall be prepared,. approved and distribu at Minutes to the tach NSEG._meethg

~^"+4"a "4-a Drae4daa+shalLhe,_preppted, approved _.

and forwarded ona "= + mne ="d i Nuclear

~

"f) Vi I perat15NItiiin Iidaysio'lTow'ing"'iiacil meeting.ce President' +

b.

Reports of reviews encompassed by Se *

.7 above_. phal -

.5 0= d and forwarded to the % cy+4"a Vy a 3",ac W "+ ona"=-

and th Vice President, Nuclear ope 73tions wi in T6wT6Mifmpletion of the review.

c. Audit summary reports e forwarded to the NSRC, hc Excc asse4hy section-6 5 2JLabove,_Qall be -

the Vice President, Nuc Fear OM"+ 4"-'! s. ice Fulll' audits ras i" ant, s alOper:+ iem and l e forwarded to the management positions responsible' for the areas audited within 30 days after completion of the audit by the auditing organization.-

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a.

Procedures required by Technical Specification 6.8 and other proce-dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the

! individual / group which prepared the procedure or procedure change, but i who~may be from the same organization as the individual / group which prepared the procedure or procedure change. Procedures other than l Administrative Procedures will be approved as delineated in writing by the General Manager, Nuclear Plant-0perations.

1 Nuclear Plant Operations will approve administrative procedures,The l Gen security implementing procedures and emergency plan implementing procedures.

Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change, b.

Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the General Manager, Nuclear Plant Operations. i Each such modifica- I tion shall be designed as authorized by Engineering Services and shall be reviewed by an individual / group other than the individual /

group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications.

Implementation of modifications to plant nuclear safety related structures, systems and components shall be concurred in by the General Manager, Nuclear Plant Operations. l SUMMER - UNIT 1 6-9 Amendment No. 35, 79 y & = wiu w e w- - = n un e- v s- so=' s-A

. 1 4

ADMINISTRATIVE CONTROLS

~

RECORDS I 6.5.2.10 Records of NSRC activities shall be prepared, approved and distributed i

as indicated below
a. Minutes of each NSRC meeting shall be prepared, approved and forwarded i to the Vice President, Nuclear Operations, within 14 days following l l each meeting. I i
b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be pre- I pared, approved and forwarded to the Vice President, Nuclear Operations, within 14 days following completion of the review.
c. Audit summary reports encompassed by Section 6.5.2.8 above, shall be forwarded to the NSRC and the Vice President, Nuclear Operations. l Full audits shall be forwarded to the management positions responsible '
for the areas audited within 30 days after completion of the audit by I the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ,

l ACTIVITIES l 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows: i

a. Procedures required by Technical Specification 6.8 and other proce-
dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but  !

who may be from the same organization as the individual / group which j prepared the procedure or procedure change. Procedures other than Administrative Procedures will be approved as delineated in writing by the General Manager, Nuclear Plant Operations. The General Manager,

, Nuclear Plant Operations will approve administrative procedures, security implementing procedures, and emergency plan implementing procedures. Temporary approval to procedures which clearly do not change the intent of the approved procedures can be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License. For changes to procedures which l 1

may involve a change in intent of the approved procedures, the person authorized above to approve the procedures shall approve the change.

b. Proposed changes or modifications to plant nuclear safety-related -

structures, systems and components shall be reviewed as designated by (

the General Manager, Nuclear Plant Operations. Each such modifica- l tion shall be designed as authorized by Engineering Services and '

shall be reviewed by an individual / group other than the individual / l group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications.

Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the General Manger, Nuclear Plant Operations.

l I

SUMMER - UNIT 1 6-9 Amendment No. 18, 35, 79 l

l .

ADMINISTRATIVE CONTROLS

d. i Critical by operation the Commission. of'the unit shall not be resumed until authorized 6.8 PROCEDURES AND PROGRAMS ,'
6. 8.1 covering Written procecures the activities shall below:

referencea be established, implemented and maintained

a. j b.

Guide 1.33, Revision 2, February 1978.The applicable pro Refueling operations.

c. (
d. Surveillance Security Plan. and test activities of safety related equipment.

l

e. Emergency Plan.

f.

Fire Protection Program.

g.

h.

PROCESS CONTROL PROGRAM. ,

i. OFFSITE DOSE CALCULATION MANUAL. l Effluent and environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.

6.8.2 )

JJ Each proceaure m of 6.8.1 above, and changes'thereto, shall be reviewed on as set forth in 6.5 above.

6. 4 The to owing programs shall be estab'lished, implemented, and maintaineo:,

a.

Primarv Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside serious transient or accident to as low as The practical level systems include tae chemical and volume control, letd i

handling The progr,am shall include the following: gas raawaste handling an (i) Preventive maintenance and periodic visual inspection 1 reovirements, and (ii) Integrated leakortest cycle intervals requirements for each system at refueling less.

b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas conditions. unoer accident This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and (iii)

Provisions for maintenance of sampling and analysis eouipment.

SUMMER - UNIT 1 6-11 Amenoment No.78.II.R l 79

ADMINISTRATIVE CONTROLS

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

6.8 PROCEDURES AND PROGRAMS

^

6.8.1 Written procedures shall be established, implemented and maintained

, covering the activities referenced below:

4

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b. Refueling operations.
c. Surveillance and test activities of safety-related equipment.
d. Security Plan.

e.

Emergency Plan.

f. Fire Protection Program.

I g. PROCESS CONTROL PROGRAM.

! h. 0FFSITE DOSE CALCULATION MANUAL.

1. Effluent and environmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed prior to implementation as set forth in 6.5 above.

6.8.3 NOT USED. l 4

6.8.4 The following programs shall be established, implemented and maintained:

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The
systems include the chemical and volume control, letdown, safety injection, residual heat removal, nuclear sampling, liquid radwaste handling, gas radwaste handling and reactor building spray system.

The program shall include the following:

(1) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitoring (i Training of personnel, (11 Procedures for monitoring, and
(iii Provisions for maintenance of sampling and analysis equipment.

SUMMER - UNIT 1 6-11 Amendment No. 18, 49, 72, 79

i ADMINISTRATIVE CONTROLS

c. Secondarv Water Chemistry i

A program for monitoring of secondary water chemistry to inhibit '

steam generator tube degradation. This program shall include:

(i) Identification of a sampling schedule for the critical variables  !

and control points for these variables, i (ii) Identification of the procedures used to measure the values of the critical variables, -

(iii) Identification of process samoling points, including monitoring i

the discharge of the condensate pumps for evidence of condenser in-leakage.

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

(v) Procedures defining corrective actions for all off-control point chemistry conditions, (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Postaccident Samoling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant

' gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training personnel, (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

e. Radioactive Effluent Controls Prooram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents achievable. The program (1) shall be contained C ( as reasonably (2) shall be {

imolemented by operating procedures, and (3) shall inc de remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous

' monitoring instrumentation including surveillance tests and setpoint determinations in accordance with the methodology in the ODCM,

2) Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conformi T10 CFR Part 20, Appendix B, Table II, Column 2; i

SUMMER - UNIT 1 6-12 Amenoment No. 33.'57-79, 104

l ADMINISTRATIVE CONTROLS l

c. Secondary Water Chemistry l l

A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

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

(ii) Identification of the procedures used to measure the values of the critical variables.

(iii) Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (iv) Procedures for the recording and management of data, l (v) Procedures defining corrective actions for all off-control point l chemistry conditions, l l

(vi) A procedure identifying (a) the authority responsible for the  ;

interpretation of the data, and (b) the sequence and timing of i I

administrative events required to initiate corrective action.

d. Postaccident Samplinq A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training personnel, l (ii) Procedures for sampling and analysis, l (iii) Provisions for maintenance of sampling and analysis equipment. I

e. Radioactive Effluent Controls Program A program shall be provided conforming with 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 program (1) shall be contained in the ODCM, (2) shall l be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements: l
1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determinations in accordance with the methodology in the ODCM,
2) Limitations on the concentration of radioactive material released in liquid effluents to unrestricted areas conforming to l 10 CFR Part 20, Appendix B, Table II, Column 2; SUMMER - UNIT 1 6-12 Amendment No. 18, 35, 57, 79, 104

a l

ADMINISTRATIVE CONTROLS e.

! Radioactive Effluent Controls Prooram (Continued) 1

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accoroance with 10 CFR 20.106 and with the methodology and parameters in the ODCM; i
4) Limitations on the annual and quarterly doses or dose commitment
to a member of the public from radioactive materials in liquid '

effluents released to unrestricted areas conforming to Appendix I to 10 CFR Part 50.

5) Determinationofcumulative:andprojecteddosecontributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days-
6) Limitations on the operability and use of the liquid and gaseous I effluent treatment systems to ensure that the appropriate  !

portions of these systems are used to reduce releases or radioactivitywhentheprojecteddosesina31-dayperiodwould exceed 2 percent of the guidelines for the annual or dose commitment conforming to Appendix I to 10 CFR Part 50;

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR Part 20, Appendix
B, Table II, Column 1;
8) l Limitations on the annual and quarterly air doses resulting from I noble gases released in gaseous effluents to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50; 1
9) Limitations on the annual and quarterly doses to a member of the public from Iodine-131, Iodine-133, tritium, and all i

radionuclides in particulate from with half-lives greater than 8  !

days in gaseous effluents released to areas beyond the site bounoary conforming to Appendix I to 10 CFR Part 50;

10) Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
f. Radiolooical Environmental Monitoring Prooram A program shall be provided to monitor the radiation and

- radionuclides in the environs of the pla t-gThe program shall provide (1) representative measurement radioactivity in the I highest potential exposure pathways, and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be containeo , ,

in ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, samoling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; SUMMER - UNIT 1 6-12a Amendment No. 104

l ADMINISTRATIVE CONTROLS i l

e. Radioactive Effluent Controls Program (Continued) l l

, 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM;

4) Limitations on the annual and quarterly doses or dose commitment i to a member of the public from radioactive materials in liquid effluents released to unrestricted areas conforming to Appendix I to ;1 CFR Part 50;
5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and i parameters in the ODCM at least every 31 days;  ;
6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate

. portions of these systems are used to reduce releases or

! radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual or dose commitment conforming to Appendix I to 10 CFR Part 50;

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1; i
8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50;
9) Limitations on the annual and quarterly doses to a member of the public from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate from with half-lives greater than 8 days in gaseous effluents released to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50;
10) Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
f. Radiological Environmental Monitorina Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measures of radioacMvity in the l highestpotentialexposurepathways,and(2)veriticationofthe accuracy of the effluent monitoring program a,'d modeling of environmental exposure pathways. The program shall (1) be contained in the 00CM, (2) conform to the guidance of Appendix 1 to 10 CFR Part l 50, and (3) include the following:
1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; SUMMER - UNIT 1 6-12a Amendment No. 104

I ADMINISTRATIVElDNTROM ~ _ - - --- -

Tt f.

MiO l@(CCLI Environtne>wl (DOni+0rcng Rcdiccctive Ef#'.utr.: Controls Prooram (Continued)

2) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of the census; and
3) Participation in an Inter-52boratory Comparison Program to ensure that independent checks on the precision and accuracy of 1

measurements of radioactive materials in environmental sample i matrices are performed as part of the quality assurance program for environmental monitoring.

SUMMER - UNIT 1 6-12b Amenoment No. 104

l ADMINISTRATIVE CONTROLS

f. Radiological Environmental Monitorina Program (Continued) l
2) A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of the census; and
3) Participation in an Inter-laboratory Comparison Program to ,

ensure that independent checks on the precision and accuracy of j measurements of radioactive materials in environmental sample i matrices are performed as part of the quality assurance program j for environmental monitoring.

l I

1 l

l 1

. l l

\

l l t

1 l

l 1

l l

SUMMER - UNIT 1 6-12b Amendment No. 104

, i

  • 1 i .

ADMINISTRATIVE CONTROLS This report shall also include the results of specific activity analysis in which the primary coolant exceeoed the limits of Specification 3.4.8. 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; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow 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; (4) GraptL of the-I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant l

exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

6. 9.1. 6 The annual radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3 and IV.C of Appendix 1 to 10 CFR Part 50.

9 used.

Anntut l SEMI " Uf' 010 ACTIVE EFFLUENT RELEASE REPORT

"(4nno l 6.9.1.8 '

dioactive nt release report covering the operation  !

of the un bmiariring the previou ' gnt within 60 days after January 1 anc llof _u.y%f each operation year. shall be submitted ,

j SUMMER - UNIT 1 6-14 Amendment No. 77, 104

ADMINISTRATIVE CONTROLS This report shall also include the results of specific activity analysis in which the primary coolant exceeded the limits of specification 3.4.8. 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; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow 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; (4) Graph of the I-131 concentration and one i other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4

6.9.1.6 The annual radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and an analysis of trends 4

of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the 02CM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

6.9.1.7 Not used.

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Annual radioactive effluent release report covering the operation

! of the unit during the previous 12 months of operations shall be submitted within 60 days after January 1 of each year.

j The report shall include a summary of the quantities of radioactive liquid and i gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

4 SUMMER - UNIT 1 6-14 Amendment No. 64, 79, 104

I ADMINISTRATIVE CONTROLS

?u3 The report shall include 5 summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provi- p ded shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I i 10 CFR Part 50.

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i SUMMER - UMIT 1 6-15 Amenament No. gg, 7g 104

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SUMMER - UNIT 1 6-15 Amendment No. 64, 79, 104

r l ADMINISTRATIVE CONTROLS

6. 9.1. 9 Not used.

. MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, in-ciuding documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, l U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no.later than the 15th of each month following the calendar month covered by the report.

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Any-enangne to the OEESLTE-DOSHALCULaTION MANttAt. 'siisil bt: suumitted with-the3 Honttrty-Operating-R 9 pert uitMrdiays jpMeh-the ghappeRwgs_-madef~(

e" ctive. .rcedditiet eport of any major changes to the radioact1ve waste  ;

treatment systems s a e submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 aoove.

CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a. Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm surveillance limit for Specification ~ 3/4.1.1.3, ,
b. Shutdown Bank Insertion Limit for Specification 3/4.1.3.5,
c. Control Bank Insertion Limits for Specification 3/4.1.3.6,
d. Axial Flux Difference Limits, target band, and APLND for Specification 3/4.2.1,
e. ND HeatFluxHotChannelFactor,Ff,K(Z),W(Z),APL and W(Z)BL for Specification 3/4.2.2,
f. Nuclear Enthalpy Rise Hot Channel Factor, F and Power Factor l Multiplier, PFg, limits for Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

a. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (W Proprietary).

l SUMMER - UNIT 1 6-16 Amencment No. 7g, gg, 104

ADMINISTRATIVE CONTROLS 4

j 6.9.1.9 Not used.

l l MONTHLY OPERATING REPORT t

j 6.9.1.10 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORV's or safety valves, shall

be submitted on a monthly basis to the Director, Office of Resource Management, j U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each
month following the calendar month covered by the report.

i A report of any major changes to the radioactive waste treatment systems shall

be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above.
CORE OPERATING LIMITS REPORT

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6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

$ a. Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,

b. Shutdown Rod Insertion Limit for Specification 3/4.1.3.5, j c. Control Rod Insertion Limits for Specification 3/4.1.3.6,

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d. Axial Flux Difference Limits, target band, and APLND for Specification 3/4.2.1, RTP ND l' e. Heat Flux Hot Channel Factor, Fq ,K(Z),W(Z),APL and W(Z)BL
for Specification 3/4.2.2, RTP j f. Nuclear Enthalpy Rise Hot Channel Factor, FaH, and Power Factor Multiplier, PFaH, limits for Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described j in the following documents:

a. WCAP-S272-P-A', " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

l July 1985 (W Proprietary).

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l SUMMER - UNIT 1 6-16 Amendment No. 35, 49, 75, 79, 88, 104 1

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$ ADMINISTRATIVE CONTROLS

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

] 6.14.2 Changes to the ODCM:

! a. Shall be documented and records of reviews performed shall be i

retained as required by Specification 6.10.2.o. This documentation '

shall contain: l

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

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2) A determination that the change will maintain the level of '

' radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and 3

not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.

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b. Shall become effective after review and acceptance by the PSRC and  !

] the approval of the General Manager, Nuclear Plant Operations. I

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c. Shall be submitted to the Commission in the form of a complete eg' 1  !

y of the entire ODCM as a part of or concurrent with the pg3nu;c{Sc:i:nne2 Radioactive Effluent Release Report for the period of the

--+epot in which any change to the ODCM was made.

i Each change shall be identified by markings in the margin of the affected pages,

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clearly indicateindicating (the month the date e.g., area of the page that was changed, and shall

/ year) the change was implemented.

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, SUMMER - UNIT 1 6-20 Amenoment No. J7, 79,104 i

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ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) l l

6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o. This documentation l shall contain: 1 1
1) Sufficient information to support the change together with l appropriate analyses or evaluations justifying the change (s);

and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
b. Shall become effective after review and acceptance by the PSRC and the approval of the General Manager, Nuclear Plant Operations.
c. Shall be submitted to the Commission in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

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SUMMER - UNIT 1 6-20 Amendment No. 16, 35 41, 79, 104,

a Enclosure 2 to Document Control Desk Letter TSP 930016 Page 1 of 2 SAFETY EVALUATION FOR VIRGIL C. SUMMER NUCLEAR STATION Description of Amendment Request:

The proposed amendment to Technical Specification 6.3, " Unit Staff Qualifications," 6.4, " Training," 6.5.2, " Nuclear Safety Review Committee,"

6.5.2.8, " Audits," 1.17 and 6.9.1.8, " Semiannual Radioactive Effluent Release Report," 6.9.1.10 " Monthly Operating Report," 6.14, "Offsite Dose Calculation Manual," and typing revisions to pages 1.4, 1.5, 3/4 3-26 Footnote, 3/4 3-30 Table 3.3.5, 3/4 3-34 Table 3.3-5, 3/4 3-67 sections 3.3.3.9.a and 3.3.3.9.b, 3/4 3-70 section 1.a and 1.b, 6-11 section 6.8.3, 6-12 sections 6.8.4.e and 6.8.4.e.2, 6-12a section 6.8.4.f and 6-12b section 6.8.4.f are administrative in nature in that:

1. The submittal of the Radioactive Effluent Release Report should be submitted annually rather than semiannually, i
2. Changes to the Offsite Dose Calculation Manual (0DCM) should be submitted in the Radioactive Effluent Release Report and not in the l

monthly operating report, j 3. Implementation of Strategic Business Units at South Carolina Electric l & Gas Company has resulted in positions being reassigned. The position of Executive Vice President, Operations, has been deleted. The Nuclear Safety Review Committee reported to the Executive Vice President, Operations, which requires a change to the Technical Specifications,

4. The audit frequencies will be deleted as listed in the TS. Making this change will allow Quality Systems management a more effective use of resources by providing flexibility on the scheduling of these audits that are listed in the TS,
5. The title change from Associate Manager, Health Physics to Radiation Protection Manager represents a restructuring of unit staff only,
6. To delete the reference to the March 28, 1980, NRC letter -- addressed to all licensees -- and the Shift Technical Advisor requirements l specified in Enclosure 1 of the October 30, 1979, NRC letter to all l operating nuclear power plants, l
7. To delete Technical Specification 6.4,
8. The typographical revisions are to clarify the text and to include items that were omitted in previously issued amendments.

Enclosure 2 to Document Control Desk Letter TSP 930016 Page 2 of 2 Safety Evaluation:

The proposed administrative changes to Technical Specification 1.17, 6.9.1.8, 6.9.1.10 and 6.14 are required to incorporate recent changes to the reporting requirements of 10CFR50.36(a)2 and to delete the requirement to submit changes to the ODCM in the monthly operating report. The change to 6.5.2 is required to reflect a change to the organization and to allow Quality Systems management flexibility in audit scheduling. VCSNS has established, implemented, and maintained accredited training and qualification programs for power plant personnel categories included in the 10CFR50.120 and 10CFR55 based on ACAD 91-015, The Objectives and Criteria for Accreditation of Trainino in the Nuclear Power Industry. The change to TS 6.3 is requested to reflect VCSNS conformance to the requirements of 10CFR50.120 and to reflect.

changes in the restructuring of unit staff. The typing revisions are required to clarify text previously revised under Amendments 88 and 104.

The proposed changes do not alter the plant configuration and requirements, methods or manner of plant operation, or affect any technical specification margin of safety. Pursuant to the above information, this amendment request does not adversely affect or endanger the health or safety of the general public and does not involve an unreviewed safety question.

e Enclosure 3 to Document Control Desk Letter TSP 930016 Page 1 of 2 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION Description of Amendment Request:

The proposed amendment to Technical Specification 6.3, " Unit Staff Qualification," " Training," 6.5.2, " Nuclear Safety Review Committee,"

6.5.2.8, "Audi, 17 and 6.9.1.8, " Semiannual Radioactive Effluent Release Report," 6.9.1.lb, donthly Operating Report," 6.14. "Offsite Dose Calculation Manual," and typing revisions to sections to pages 1.4, 1.5, 3/4 3-26 Footnote, 3/4 3-30 Table 3.3.4, 3/4 3-70 section 1.a and 1.b, 6-11 section 6.8.3, 6-12 sections 6.8.4.e and 6.8.4.e.2, 6-12a section 6.8.4.f and 6-12b section 6.8.4.f are administrative in nature in that:

1. The submittal of the F .tive Effluent Release Report should be submitted annually ratim. . nan semiannually,
2. Changes to the Offsite Dose Calculation Manual (0DCM) should be submitted in the Radioactive Effluent Release Report and not in the monthly operating report,
3. Implementation of Strategic Business Units at South Carolina Electric &

Gas Company has resultad in positions being reassigned. The position of Executive Vice Presit Operations, has been deleted. The Nuclear Safety Review Committe reported to the Executive Vice President, Operations, which requires a change to the Technical Specifications,

4. The audit frequencies will be deleted as listed in the TS. Making this change will allow Quality Systems management a more effective use of resources by providing flexibility on the scheduling of these audits that are listed in the TS,
5. The title change from Associate Manager, Health Physics to Radiation Protection Manager represents a restructuring of unit staff only,
6. To delete the reference to the March 28, 1980, NRC letter -- addressed to all licensees -- and the Shift Technical Advisor requirements specified in Enclosure 1 of the October 30, 1979, NRC letter to all operating nuclear power plants,
7. To delete Technical Specification 6.4,
8. The typographical revisions are to clarify the text and to include items that were omitted in previously issued amendments.

i Enclosure 3 to Document Control Desk Letter TSP 930016 Page 2 of 2 Determination of No Significant Hazards Consideration:

The Licensee has evaluated the proposed amendment and has provided the following discussion:

1. The proposed amendment does not involve a significant increase in the probability or consequence of an accident previously evaluated because ,

the administrative change does not affect plant operations in any  ;

manner. ,

2. The proposed amendment does not create the possibility of a new or ,

l different kind of accident than previously evaluated because the  !

I proposed change is administrative in nature and no physical alterations l l of plant configuration or changes to setpoints or operating parameters i are proposed.  !

3. The proposed amendment does not involve a significant reduction in the i margin of safety. The change is only administrative. l Pursuant to 10CFR50.91 the preceding analyses provides a determination that the proposed change poses no significant hazard as defined by 10CFR50.92. In  :

view of the preceding,-South Carolina Electric & Gas Company has determined that the proposed license amendment does not involve any significant hazards ,

considerations.

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