ML20063G912

License NPF-12 Authorizing Facility Operation at 2,775 Mwt

ML20063G912
Person / Time
Site:	Summer
Issue date:	08/06/1982
From:	Harold Denton Office of Nuclear Reactor Regulation
To:
Shared Package
ML19253F583	List: ML19253F582 ML20063G912 ML20063G916 ML20063G925
References
NUDOCS 8209010232
Download: ML20063G912 (15)

Text

___ _ _ _

SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PubLIC SERVICE AUTHORITY DOCKET h0. 50-395 VIRGIL C. SUlViEh huCLEAR STATION, UNIT N0. 1 FACILITY OPERATI% LICENSE License No. HPF-12 1.

The Nuclear Regulatory Comission (the Comission or the HRC) having found that:

A.

The application for a license filed by South Carolina Electric

& Gas Conpany acting for itself and South Carolina Public Service Authority (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Virgil C. Summer Nuclear Station, Unit No.1 (the facility) has been substantially completed in confornity with Construction Pernit No. CPPR-94 and the application, as anended, the provisions of the Act, and the regulations of the Comission; C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Connission; D.

There is reasonable assurance:

(1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations:

l set forth in 10 CFR Chapter I; E.

South Carolina Electric & Gas Conpany* is technically qualified to engage in the activities authorized by this operating license in accordance with the Comission's regulations set forth in 10 l

CFR Chapter I; F.

The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indennity Agree,1 s

ments", of the Comission's regulations; L

i i

G.

The issuance of this license will not be inimical to the comon s

defense and security or to the health and safety of the public; x

3 8209010232 820806 fDRADOCK 05000393 r wn,, F DR

,y

,, 4

,, y

• % th 61........th..h..

. (.iU1.......t...fl.0.h......h..

..Yo.9.k...k...(.$.

.9.9.h..........

OF F #Ce )

over ep 1ys cons uc on, operat n and maintenance of and.....fr

. con g

• • ~~~~~~

" " " " ~ ~ " " " -

" " ~ " ~ " " " ~

sunnaue>

..~the" faci 1 1tyu ~ - ~~~

~~ -

.......~

~ ~ - ~.

- - ~ " " -

oare y OFFICIAL RECORD COPY uso o:un-m m NRC FORM 318 (10-80) NRCM 024a

"V%

, 1 11.

After weighing the environmental, economic, technical, and other benefits of the facility against environnental and other costs and considering available alternatives, the issuance of Facility Operating License NPF-12, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51, of the Comiission's regulations and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.

2.

Based on the foregoing findings regarding this facility, the Partial Initial Decision issued by the Atomic Safety and Licensing Board on i

July 20,1982, and the Supplemental Partial Initial Decision issued by the Atomic Safety and Licensing Board on August 4,1982, Facility Operating License No. NPF-12 is hereby issued to the South Carolina Electric & Gas Company and the South Carolina Public Service Authority (the licensees) to read as follows:

A.

This license applies to the Virgil C. Summer Nuclear Station, Unit 1, a pressurized water reactor and associated equipment (the facility), owned by the South Carolina Electric & Gas Company and South Carolina Public Service Authority. The facility is s

located in Fairfield County, South Carolina, and is described in South Carolina Electric & Gas Company's Final Safety Analysis T

Report, as anended through Amendment No. 33, and the Environmental Report, as anended through Amendment No. 5.

b.

Subject to the conditions and requirements incorporated herein,.

i the Commission hereby licenses-d t

(1) South Carolina Electric & Gas Company (SCE4G), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Fairfie'(d g

County, South Carolina, in accordance with the procedures

(

N l

and limitations set forth in this license;

\\L (2) South Carolina Public Service Authority to possess the facility '

s at the designated location in Fairfield County, South Carolina, i

in accordance with the procedures and limitations set forth in this license; (3) SCE&G, pursuant to the Act and 10 CFR Part 70, to receive, 3 possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as anended through Amendment No. 33; ornce>

SURNAME >

one>

........... ~..

... ~....... ~ ~.

unc rono ais o>em nacu om OFF1ClAL RECORD COPY Usom mi-mm

.=.

. 4 (4) SCElG, pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in anounts as required; (5) SCE&G, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for saaple analysis or instrument Cdlibration or associated with radioactive apparatus or components; and (6) SCE&G, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain, and is subject to, the conditions specified in the Connission's regulations set forth in 10 CFR Chapter I dnd is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional Conditions specified or incorporated below:

(1)

Maximum Power Level SCE&G is authorized to operate the facility'at reactor core power levels not in excess of 2775 megawatts thermal in accordance with the conditions specified herein and in Attachment i

1 to this license. The preoperational tests, startup tests and other itens identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license. Pending Conmission approval, this license is restricted to power levels not to exceed 5 percent of full power (139 negawatts thermal).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. SCEaG shall operate the facility in accordance -

with the Technical Specifications and the Environnental Protection P1an.

4 y

ornce>

......... ~

tuam e >

we >

.... ~........

nac ronu ais oo-aoi nacu ous OFFICIAL RECORD COPY usam msuwe

4 i

.4-(3)

Conduct of Work Activities During Fuel Load and Initial Startup SCE&G shall review by committee all facility construction, preoperational testing, and system demonstration activities performed concurrently with facility initial fuel loading or with the facility startup test program to assure that the i

activity will not affect the safe performance of the facility fuel loading or the portion of the facility startup program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security, and health physics, with respect to performance of the activity concurrently with the facility fuel loading or the portion of the facility startup progran being performed. The committee for the review shall be composed of at least three i

members, knowledgeable in the above areas, and who meet the qualifications _ for professional-technical personnel specified by Section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Plant Manager's itsff.

i (4)

Initial Test Program SCE3G shall conduct the post-fuel-loading initial test program set forth in Chapter 14 of the Final Safety Analysis Report, as amended through Amendment No. 33, without making any major modifications to this program unless such modifications have been identified and have received prior NRC staff approval.

Major modifications are defined as:

a.

Elimination.of any test other than those identified as non-essential in Chapter 14 of SCE&G's Final Safety Analysis Report, as amended through Amendment No. 33, t

b.

Modification of test objectives, methods or acceptance criteria for any test other than those identified as non-essential in Chapter 14 of SCE&G's Final Safety Analysis Report, as amended through Amendment No. 33,

\\

i c.

Performance of any test at a power level different from

\\

the power level indicated in the described program; and

[

t d.

Failure to conolete any tests included in the described

\\

I program (planned or scheduled for power levels up to i

the authorized power level).

Ql For the performance of startup testing as described in Table.

14.1-75 of the Final Safety Analysis Report, as amended through Amendment No. 33, compliance with items 3 and 4 of Table 3.3-1 F

of the Technical Specifications is not required.

4 l

omce>

l suame >

ocre>

OFFICIAL RECORD COPY usamm-muo i nac ronu sia no.8cancu oua

. ~

~

i

\\

_5-(5)

Stability of the West Embanknent and its Effects on the Intake Structure (Section 2.5.4, SSER 3)

SCE3G shall conduct the monitoring progren discussed in Section 2.5.4.10.6.2 of the Final Safety Analysis Report, as amended through Amendment No. 33, to specifically include the following:

J a.

At the vicinity of the pumphouse and intake structure, four settlement points capable of monitoring both horizontal and vertical movenents shall be established to monitor the enbankment novenents.

b.

The submerged slope profile of the west enbankment over the intake structure shall be established and monitored to detect any unusual movements that may affect the intake structure.

c.

The condition of the intake structure shall be nonitored to detect new cracks and changes to the old, grouted or ungrouted cracks. Should any cracks wider than 0.015 inch be discovered, the extent and size of such cracks shall be reported by SCE5G to the NRC staff along with a plan for remedial action. Such inspections shall also be conducted imnediately following any earthquake during which the plant seismic instrumentation indicates that the operating basis earthquake has been exceeded.

d.

The schedule and the reporting requirements of the above inspection shall be in accordance with the reconnendations stated in Regulatory Guide 1.127.

(6)

Design Verification Program (Section 3.7.4, SSER 4)

Prior to exceeding 5 percent of full power, SCE&G shall provide, for NRC staff review and approval, the final report i

of the design verification progran being conducted on the emergency feeduater systen.

(7)

Thernal Sleeves (Section 3.9.3, SSER 4)

Prior to exceeding 5 percent of full power, SCE&G shall provide', ' '

for NRC staff review and approval, justification for the renoval\\

of the thernal sleeves from selected nozzles in the reactor coolant systen.

s (8)

Environmental Qualification of Mechanical and Electrical Eouipment (Section 3.11, SSER 4) i a.

SCE&G shall complete all actions related to environnental quail rication or equipment on a schedule spccified in Sec tion omcs >

............ 3 LL.af..Suppic. aat Ko.. 4..to..the 5a faty.. Eval ( a tien Gepert, suaseue >

4 oon y unc ronu ais oo.aoi nncu oao OFFICIAL RECORD COPY usam mi-m*o

+

I D

, b.

Complete and auditable records shall be available and naintained at a central location by SCE8G. Such records shall describe the environmental qualification methods used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," Revision 1, dated July 1981. Such records shall be updated and naintained current as equipnent is replaced, further tested, or otherwise further qualified to document compliance with NUREG-0588.

c.

Prior to startup after the first major shutdown or refueling outage af ter June 1983, SCE&G shall be in compliance with the provisions of HUREG-0588 for safety-related electrical equipment exposed to a harsh environment.

(9)

Mechanical Performance (Section 4.2.3, SER)

Prior to startup after the first refueling outage, SCE&G shall examine _ fuel rods for baffle-jetting failure as specified in Section 4.2.3 of the Safety Evaluation Report. Should damage be observed at that time, a corrective action plan shall be submitted to the HRC staff for review and approval.

(10)

Overpressurization Protection (Section 5.2.2, SSER 4)

Prior to startup after the first refueling outage, SCEAG shall install an HRC staff-approved low-temperature. overpressurization protection system. The preliminary design shall be provided i'

for ilRC staff review not later than June 30, 1983.

x (11)

Inservice Inspection and Testing (Section 5.2.4, SSER 3)'

i

\\

SCEAG shall perforn the following actions in conjunction with the

(

first inservice exanination:

Demonstrate the ability of the ~ ultrasonic exaaination prochdure k a.

to detect actual flaws and/or artificial reflectors in theN i

volume subject to examination to the acceptance standards bf

\\

Paragraph IWB-3500 in weldments representative of the design N

and naterials of construction.

1

-t b.

In the event that one-third thickness sent-circular reference flaws cannot be detected and discrininated from inherent 1

anonalies, the entire volume of the weld shall be exanined

/

K-during the inservice inspection.

omen p

. -....... ~.

~~.. ~..

.. -. ~ -

SURNMn) m..~

.....m~

m.

m e.-~

~~.--

a="

~~

- * " " ~ * * -

omny

.. - ~ ~ ~ ~. -

- - - - ~ ~ ~.

e,nc ronu ate now uncu oua OFFiClAL RECORD COPY usom ini-mm

s t

, c.

The reporting of the inservice inspection examination results shall be documented in a manner to define qualitatively whether, the weldment and the heat affected zone and adjacent base netal on both sides of the weld were examined by ultrasonic angle beam techniques.

(12) Design Description - Control (Section 4.3.2, SER)

SCE&G is prohibited from using part-length rods during power operation.

(13) Stean Generator Inspection Ports (Section 5.4.2, SER)

Prior to startup after the first refueling outage, SCE&G shall install steam generator inspection ports at the locations specified in Section 5.4.2 of the Safety Evaluation Report unless justification is submitted to the NRC staff for not installing such ports and written approval is given by the NRC staff.

(14) Model D-3 Steam Generators (Section 5.4.2, SSER 4)

Prior to exceeding 5 percent of full power, SCE&G shall provide a detailed program for operation for HRC staff review and approval pending the implementation of design nodifications to correct potentially damaging tube vibrations.

(15) Residual Heat Removal System (Section 5.4.3, SSER 3)

Prior to startup after the first refueling outage, SCE&G shall complete the installation of the desi n nodification to the 5

residual heat removal systen suction valves described in Section 5.4.3 of Supplement No. 3 to the Safety Evaluation Report..

(16) Cable Tray Senaration (Section 8.3.3, SSER 4)

Prior to startup after the first refueling outage, SCEAG i

shall implement the modifications to the cable trays discussed in Section 8.3.3 of Supplement No. 4 to the Safety Evaluation Report or demonstrate to the NRC staff that faults induced in non-Class 1E cable trays will not result in failure of cable

\\

in the adjacent Class 1E cable trays.

x (17) Alternate Shutdown System (Section 9.5.1, SSER 4) s N

Prior to startup after the first refueling outage, SCE3G shall install a source range neutron flux nonitor independent of the control conplex as part of the alternate shutdown systen.

OFFICE )

suaee=E )

ocu >

NRC FORM 318 00-80) NRCM 0243 OFFiClAL RECORD COPY usam im_m

Y

, (18) Fire Protection System (Section 9.5.1, SSER 4) a.

SCE&G shall maintain in effect, and fully implenent, all provisions of the approved fire protection plan, as ar. ended through Amendment No. 33 to the Final Safety Analysis Report.

In addition, SCE&G shall maintain the fire protection program set forth in Appendix R to 10 CFR Part 50, except for the following:

(i)

Twenty-foot separation need not be maintained between component cooling water pumps B and C.

(ii)

Twenty-foot separation need not be maintained between heating, ventilation, and air conditioning system chilled water pumps.

(iii) No automatic fire suppression systems are required in the areas listed in Supplement No. 4 to the Safety Evaluation Report.

(iv)

No automatic fire detectors are required in the-areas listed in Supplement No. 4 to the Safety Evaluation Report.

b.

Prior to startup after the first refueling outage, SCE8G shall install and make operable a fire detection system in the areas listed in Table 9-1 of Supplement No. 4 to the Safety Evaluation Report. Pending installation of the fire detectors in these areas the following actions shall be taken:

(i)

Prior to initially exceeding 5 percent of full power, SCE&G shall, in lieu of Section 3.3.3.7 of the Technical Specifications, establish a fire watch patrol to inspect each area every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in accordance with Section 9.5.1 of Supplement No. 4 to the Safety Evaluation Report.

(ii) For all operating conditions subsequent to initially exceeding 5 percent of full power, SCESG shall comply with Section 3.3.3.7 of the Technical Specifications.

(19) Instrument and Control Vibration Tests for Emergency Diesel Engine Auxiliary Support hystems (Section 9.5.4, SER)

Prior to startup af ter the first refueling outage, SCE3G shall i

^

either provide test results and results of analyses to the NRC staff for review and approval which validate that the skid-mounted L rnntrol nanpl e and mner'ited ontrinnient havo hono rin u gi n.w d

tactad,

)(

orrice )

sunucue )

04re )

+

nnc rORM 318 00M NRCM cm OFFICIAL RECORD COPY usomm)-ap

U t

1 9_

and qualified for operation under severe vibrational stresses encountered during diesel engine operation, or SCEaC shall floor mount the control panels presently furnished with the diesel generators separate from the skid on a vibration-free floor area.

(20) Solid Radioactive Waste Treatment Systen (Section 11.2.3, SSER 4)

SCEAG shall not ship " wet" solid wastes from the facility until the NRC staff has reviewed and approved the process control program for the cement solidification system.

(21) Process and Effluent Radiological Monitorino and Sampling Systens (Section 11.3, SSER 4)

Prior to startup after the first refueling outage, SCEAG shall install and calibrate the condensate denineralizer backwash effluent monitor RM-L11.

(22) Core Reactivity insertion Events (Section 15.2.4, SSER 4)

For operations above 90% of full power, SCE8G shall control the reactor manually or the rods shall be out greater than 215 steps until written approval is received from the NRC staff authorizing removal of this restriction.

(23) NUREG-0737 Conditions (Section 22)

SCEAG shall complete the following conditions to the satisfaction of the NRC staf f.

Each iten references the related subpart of Section 22 of the SER and/or its supplements.

a.

Procedures for Transients and Accidents (I.C.1, SSER 4)

Prior to startup after the first refueling outage, SCE&G shall implement energency operating procedures based on guidelines approved by the HRC staff.

b.

Special Low Power Testing and Training (1.G.1, SSER 4) 4 Within twelve months following completion of the startup

(

test program, SCE&G shall provide a report describing the 3

results of a comparison of actual plant data taken during p

the natural circulation test program to the simulator responses described in the SCEAG letter, T. C. Nichols, Jr. to li. R. Denton I

dated March 31, 1982.

\\

\\

N omca>

SURNAME) omy nse ronu sia co-ao nacu 024o OFFICIAL RECORD COPY usom mi-mea

~

, c.

Direct Indication of Safety Valve Position (II.D.3, SSER 4)

Prior to exceeding 5 percent of full power, the safety valve position indication system shall be scismically qualified by SCE&G consistent with the component or system to which it is attached, and documentation of this shall be provided to the NRC staff for review and approval.

d.

Inadequate Core Cooling Instruments (II.F.2, SSER 4)

Prior to startup after the first major shutdown or refueling outage after June 30,1983, SCE8G shall complete upgrading of the incore thernocouple wiring and qualification of isolators, reference junction boxes and connectors.

e.

Plant-Specific Calculations for Compiiance with 10 CFR 1

5ection 50.46 (II.K.3.31, SSER 1)

Within one year after nodel revisions are approved by the NRC staff SCE&G shall provide a supplemental plant-specific analysis to verify compliance with 10 CFR 50.46, using the revised models developed under item II.K.3.30 of HUREG-0737.

f.

Upgrade Emergency' Support Facilities (III.A.1.2, SSER 4)

SCE&G shall complete its energency response facilities as follows:

(1)

Safety parameter display system - April 1,1983 (11)

Energency operations facility - April 1,1983 (iii) Technical support center - April 1,1983 (24) Seismic Monitoring Prograo (ASLB Partial Initial Decision, July 20,1982, 5ection VI.1)

SCEAG shall continue the seismic monitoring program discussed in Section 2.5.3 of the Safety Evaluation Report until December 31, 1983, at which time there shall be a reevaluation of the need for further monitoring to be made an additional licensing requirement.

(25) Confirnatory Seismic Analysis (ASLB Partial Initial Decision, July 20, 1962,Section VI.2)

During the first year of operation, SCE&G shall sucessfully coatolete the confirmatory prograat on plant equipment and components within the guidelines established in the findings contained in the ASLB Partial Initial Decision dated July 20, o mcw>

suaucue>

one>

OFF1ClAL RECORD COPY usceo; au-ameo nnc ronu aia cow nacu oao

i l

l

~/

l

! 1982, to demonstrate to the NRC staff's satisfaction that explicit safety margins exist for each component necessary for shutdown and continued heat removal in the event of the maximum potential shallow earthquake.

(26) Plune Exposure Emergency Planning Zone (ASLB Supplemental Partial Initial Decision, August 4,1982, Section Vill.3)

During the first year of operation, SCE&G shall assure that the plume exposure emergency planning zone has been expanded to include the Kelly hiller, Greenbriar Headstart and Chapin Elementary schools and the energency evacuation plans have been adjusted accordingly.

(27) Transportation Planning (ASLB Supplemental Partial Initial decision, August 4,1982, Section V111.4)

During the first year of operation, SCE&G shall assure that the defects in transportation planning discussed in Finding 24 of the ASLB Supplemental Partial Initial Decision dated August 4, 1982 have been remedied..

(28) Food Pathway Contamination (ASLB Supolemental Partial Initial Decision, August 4,1982,Section VIII.6)

During the first year of operation,, SCE&G shall assure that plans to implement remedial and preventive neasures for consumer protection against food pathway contamination have been formulated and communicated to the agricultural community.

(29) Siren Alerting System (ASLB Supplenental Partial Initial Decison, August 4,1932, Section Vill./ )

Prior to exceeding 5% of full power, SCE&G shall complete installation and satisfactory testing of its siren alerting system.

(30) Eacrnency Facilities and Staffing (ASLB Supplemental Partial Initial decision, August 4,1982, Lection Vill.8)

SCE&G shall conplete the following three items related to emergency preparedness to the satisfaction of the NRC staff, consistent with Supplement No. 2 to the Safety Evaluation Report, page A-13:

(i) t!ininum shift manning requirements (ii)

Emergency response facilities (iii) Meteorological and dose assessment caoability omce >

... ~... ~.. -.

.. ~. - ~ ~

SURNAME)

.......... - ~. * * *

-. ~.. - -. *

• onre >

..... ~. ~... -

.... - -.. ~.

..... - - - ~ ~

- - ~.

nnc ronu ais po soi nncu oaa OFFICIAL RECORD COPY usc.m mi-mes

y

. (31) Final NRC Approval of Emergency Freparedness (ASLB Supolenental Partial Initial Decision, August 4,1982,Section VIII.9)

Prior to exceeding 5% of full power, final NRC staff approval of the state of emergency preparedness for the Virgil C. Sumner Nuclear Station site shall be required.

(32) Steam Generator Tube Vibration (ASLB Supplemental Partial Initial Decision, August 4,1982,Section VIII.lu)

Prior to operation at full power, SCE&G shall satisfy the NRC staff that appropriate surveillance measures and remedial action plans have been implemented with respect to the steam generator tube failure problem.

D.

An exemption to the requirements of Paragraph III.B.4 of Appendix G to 10 CFR Part 50 is described in Section 5.3.1 of Supplement No. I to the Office of riuclear Reactor Regulation's Safety Evaluation Report.

This exenption is authorized by law and will not endanger life or property or the connon defense and security and is otherwise in the public interest.

Therefore, this exenption is hereby granted. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E.

SCE&G shall naintain in effect and fully implement all provisions of the Comission-approved physical security plan, guard training and qualification plan, and safeguards contingency plan, including amendments made pursuant to the authority of 10 CFR 50.54(p). The approved plans, which contain safeguards information protected under 10 CFR 73.21, are collectively entitled, " Virgil C. Sumer Nuclear Station Physical Security Plan" Amendment 2, dated September 1980, Amendnent 3, dated October 1980, Amendnent 4, dated February 1981, Amendment 5, dated June 1981, and Amendment 6, dated December 1981; " Virgil C. Sumer Nuclear Station Training and Qualification Plan" dated January 1981 as revised April 1981; and the " Virgil C. Sumer Station Safeguards l

Contingency Plan" dated January 1981 as revised April 1981.

F.

This license is subject to the following additional condition for the protection of the environment:

Before engaging in activities that may result in a significant adverse environmental impact that was not evaluated or that is significantly x

greater than that evaluated in the Final Environmental Statement, SCE4G

?

\\

shall provide a written notification of such activities to the dRC Office of Nuclear Reactor Regulation and receive written approval from that i

office before proceeding with such activities.

1 OFFICE )

+

i sununMe) oare >

mc rORM 318 M80) NRCM 0aa OFFICIAL RECORD COPY uscaopen-m*o

5

. G.

Reporting to the Commission:

(1) SCEAG shall report any violations of the requirenents contained in Section 2, Items C(1), C(3) through (32), E and F of this license within twenty-four (24) hours by telephone and confirmed by telegram, ma11 gram, or facsimile transnission to the NRC Regional Administrator, Region II, or designee, not later than the first working day following the violation, with a written followup report within fourteen (14) working days.

(2) SCE&G shall notify the Comission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Comission.

H.

The licensees shall have and maintain financial protection of such type and in such anounts as the Commissior, shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public 1iability claims.

I.

This license is effective as of the date of issuance and shall expire at midnight nn March 21, 2013.

FOR TliE NUCLEAR REGULATORY C0!NISSION 15l Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1.

Appendix A (Technical Specifications) 2.

Appendix B (Environnental Protection Plan)

Date of Issuance: AUG G 1982 AEAB AgVfhn aVs 9 yV D

8/f/82 gh,Mpd d..53

.4.8.:.M.K...

g!P' g..@.C..'...

t4's

.o.L.u g.

.tio.eha...

nu meco jxanI82 V....

.i 8zy$(3. oar

.!s

..a.g........ p atut.....

a n.........

w.

.. -o 2.

... 8...z8 2.......... 8 L8 2......... 8t.pt.ga........

8If..

8/..../.8 2...........8z.t.ts2....

om

Nac ronu ais sio-aoi nncu o24a OFFICIAL RECORD COPY usce mi-md

j

, to License HPF-12 This attachment identifies certain preoperational tests, system demonstrations and other items which must be completed to the satisfaction of NRC Region II.

SCEAG shall not proceed without written confirmation from NRC Region 11 that the following itens have been completed in accordance with the conditions and schedules set forth below:

1.

Prior to initial criticality, SCE&G shall complete to the satisfaction of NRC Region II the following 10 CFR Part 21 identified itec:

Correct the diesel generator slow start times attributed to fuel oil header drain down (81-29-01).

2.

Prior to initial criticality, SCE&G shall complete to the satisfaction 2

of HRC Region II the following open items:

a.

Complete,the replacement of all damaged prefilters external to the containment building (82-07-03).

b.

Complete the repair and testing of diesel generator B before entering Mode 4.

3.

Prior to exceeding 5% of full power, SCE8G shall complete to the satisfac-tion of NRC Region II the requirements of the following bulletins:'

l a.

Failure of gate-type valves to close against differential presture (81-BU-02).

b.

Seismic analysis for as-built safety-related piping systens required to support operations above 5% of full power (79-80-14).

4.

Prior to exceeding 5% of full power, SCE8G shall complete to the satisfac <

tion of HRC Region II the following 10 CFR Part 21 identified items:

N a.

Westinghouse 3-inch gate valve closure failure (80-37-10) g

\\

b.

Westinghouse 4-inch gate valve closure failure (81-05-09).

N 5.

Prior to exceeding 5% of full power, SCE8G shall. complete to the satisfaction-of NRC Region II the following open items:

d.

Correct the hydrogen recombiner high hydrogen alarm set at 6% versus proposed Technical Specification limit of 2% (80-06-07).

b.

Satisfactorily complete the capability test for Fe-55 analyses of liquid i

waste saaples.

i r

l OFFICE )

SURNAME)

+.........

l one)

! unc ronu sia po-soi nncu oua OFFICIAL RECORD COPY uso m i m -an no t

~

.: )

emg, :

1 4

l !

4 l

6.

Prior to full power operation, SCE&G shall complete to the satisfaction

{

of NRC Region 11 the requirements of the following bulletin:

Audibility problems encountered during evacuation alarra in high noise area (79-BU-18).

I 1

7.

Prior to full power operation, SCE8G shall complete to the satisfaction of NRC Region II the following open item:

i l

Resolve the problera of the reactor' building temperature being greater than expected during hot functional testing (80-25-09).

j

.4 i

r

)

i i

i i

i i

i l

i l

i i

4 OFFICE) suaaus >

ose>

anc ronu ste omeomacu oso OFFICIAL RECORD COPY usam mi-mm

-._ ~.

.-