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Amend 135 to License NPF-12,changing TS for Plant Unit 1,in Response to 960416 Application,As Suppl by
	ML20128G289
Person / Time
Site:	Summer
Issue date:	10/02/1996
From:	Imbro E; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20128G181	List: ML20128G177; ML20128G289; ML20128G293;
References
	NUDOCS 9610080425
	Download: ML20128G289 (15)
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pMk p 4 UNITED STATES I j

NUCLEAR REZULATORY COMMISSION f

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WASHINGTON, D.C. 20666-0001 l

'+9 . . . . . ,o l

SOUTH CAROLINA ELECTRIC & GAS COMPANY ]

l l SOUTH CAROLINA PUBLIC SERVICE AUTHORITY l DOCKET NO. 50-395 ;

VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE l 1

i Amendment No. 135 :

! License No. NPF-12

1. The Nuclear Regulatory Commission (the Commission) has found that: 1 1

A. The application for amendment by South Carolina Electric & Gas l l Company (the licensee), dated April 16, 1996, as supplemented l l July 25, 1996, complies with the standards and requirements of the l Atomic Energy Act of 1954, as amended (the Act), and the 1 Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the j Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 l of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:

9610080425 961002 PDR ADOCK 05000395 P PDR

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-g-(2) Technical Specifications and Environmental Protection Plar.

The Technical Specifications contained in Appendix A, as revised through Amendment No. 135 , and the Environmental Protection Plan

. contained in Appendix B, are hereby incorporated in the license.

South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

I FOR THE NUCLEAR REGULATORY COMMISSION

/ y 4' Eugene V. Imbro, Director Project Directorate 11-1 1 Division of Reactor Projects - I/II l Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications i Date of Issuance: October 2,1996 l

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ATTACHMENT TO LICENSE AMENDMENT NO.135 l TO FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are indicated by marginal lines. ,

Remove Paaes Insert Paaes -

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3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 i

3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 i 3/4 6-10 3/4 6-10 l 3/4 6-1) 3/4 6-11 l B 3/4 6-1 B 3/4 6-1 B 3/4 6-3 B 3/4 6-3 6-12b 6-12b

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DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions are either:

1) Ca mble ofbeing closed by an OPERABLE containment automatic !

iso ation valve system, or

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2) Closed by manual valves blind flanges, or deactivated automatic valves securedin their closed positions, except for

' valves that are open under administrative control as permitted by Specification 3.6.4,

b. All equipment hatches are closed and sealed,

c. Each air lock is in compliance with the requirements of Specification 3.6.1.3,

d. The containment leakage rates are within the limits of Specification 6.8.4.g, and

e. The sealing mechanism associated with each penetration (e.g.,

welds, bellows, or O-rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT (COLR)is the unit s ific document that provides core operating limits for the current operating reload e.

The cycle specific core operating limits shall be determined for each load cycle m accordance with Specification 6.9.1.11. Plant operation within these operating limits is addressed in individual specifications.

DOSE EQUIVALENT I-131 !

l 1.10 DOSE EQUIVALENT I-131 shall be that concentration ofI-131 (microcurie / gram) '

which alone would produce the same thyroid dose as the quantity and isotopic mixture ofI-131, I-132,I-133 I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test i Reactor Sites."

l SUMMER -UNIT 1 1-2 Amendment No.46,44,135 i

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l 3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY !

LIMITING CONDITION FOR OPERATION i 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

. APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in ,

, COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . 1

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l l , SURVEILLANCE REQUIREMENTS I 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. Atleast once per31 days verifying that all penetrations

not capable ofbeing closed b PERABLE containment automatic isolation valves and required to closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.4. :

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b. By verifpg that each containment air lock is in compliance with the requirements ofSpecification 3.6.1.3.

c. Deleted.

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Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

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i SUMMER-UNIT 1 3/46-1 Amendment No.440;M9,135 I

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE 1

! LIMITING CONDITION FOR OPERATION 3.6.1.2. Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program.

I APPLICABILITY: MODES 1,2,3 and 4.

l ACTION:

With the measured overall inte gated containment leakage rate exceeding 1.0 La, l

' within I hour initiate action to le in HOT STANDBY withm the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore the overallintegrated l leakage rate to less than or equal to 0.75 La and the combined leakage rate for all l

penetrations subject to Type B and C tests to less than or equal to 0.60 La Prior to mereasing the Reactor Coolant System temperature above 200*F.

l SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the intervals derived through the Containment Leakage Rate Testing Program and shall be i determined per the program criteria.

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SUMMER-UNIT 1 3/46-2 Amendment No.gH9,M!G,

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Page 3/4 6-3 has been deleted. l l

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I SUMMER-UNIT 1 3/46-3 Amendment No. 4s, as,135 l

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I CONTAINMENT SYSTEMS l CONTAINMENT AIR LOCKS '

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each reactor building, air lock shall be OPERABLE with both doors closed ;

except when the air lock is bemg used for normal transit entry and exit through the containment, then at least one air lock door shall be closed.

1 APPLICABILITY: MODES 1,2,3 and 4. l 1

ACTION- !

a. With one reactor building air lock door inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the ino >erable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or loc c the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is venfied to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4. The provisions of Specification 3.0.4 are not applicable.

b. With the reactor building air lock inoperable, except as the result of an inoperable air lock door, maintam at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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SUMMER-UNIT 1 3/46-4 Amendment No. +W,135 l

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMEh"TS 4.6.1.3 Each reactor building airlock shall be demonstrated OPERABLE: ,

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a. By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

b. Deleted. l

c. At least once per six months by verifying that only one door in each airlock canbe opened at a time.

d. Deleted. l l

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SUMMER-UNIT 1 3/46-5 Amendment No. 44,135 i

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

If the inspections performed at 1,3, and 5 years indicate no abnormal I degradation of the tendon system, the number of sample tendons may be reduced I to 3 dome,3 vertical, and 3 hoop for subsequent inspections. Upon the comple-

tion of the five year inspection, the results of the first three inspections i shall be evaluated to determine if an abnormal condition is evident for the l tendon system. Based on the conclusions of this evaluation, the sample tendons l with their Base Values and Normalizing Factors will be specified for all '

l subsequentlocations.

4.6.1.6.2 At the same inspection frequency as the tendons, the structural ,

integrity of the end anchorages of all tendons inspected pursuant to Specifica- ;

tion 4.6.1.6.1 and the adjacent concrete surfaces shall be determined by a visual inspection and verifying that no abnormal material or structural behavior is evident.

4.6.1.6.3 In accordance with the Containment Leakage Rate Testing Program, ,

the s,tructural integrity of the exposed accessible interior and exterior surfaces of the containment shall be determined by a visual inspection of these surfaces l and verifying that no abnormal material or structural behavior is evident.

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SUMMER-UNIT 1 3/4 6-10 Amendment No. 135 f

P CONTAINMENT SYSTEMS l CONTAINMENT VENTILATION SYSTEM '

LIMITING CONDITION FOR OPERATION l

3.6.1.7 Each containment purge suppiy and exhaust isolation valve shall be ;

OPERABLE and:

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a. Each 36-inch containment purge supply and exhaust isolation valve i shallbe sealed closed

b. The 6-inch containment purge supply and exhaust isolation valves may be open for less than or equal to IDD0 hours per 365 days. '

APPLICABILITY: MODES 1,2,3, and 4.

ACTION: I

a. With a 36-inch containment pur and/or exhaustisolation valve (s) open or not sealed close,ge close and supply /or seal close the open valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , otherwise be in atleast HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With a 6-inch containment purge supply and/or exhaust isolation valve (s) open for more than 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months per 365 days, close the opsh 6-inch valve (s) or isolate the penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate exceeding the limits of Surveillance Requirements 4.6.1.7.3, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 Each 36-inch containment purge supply and exhaustisolation valve shallbe verified to be:

a. Closed atleast once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

b. Sealed closed at least once per 31 days.

4.6.1.7.2 The cumulative time that the 6-inch purge supyly and exhaust isolation valves have been open during the past 365 days shall be c etermined at least once per 7 days.

4.6.1.7.3 At least once per 30 months each containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE in accordance with the Containment Leakage Rate Testing Program. l SUMMER-UNIT 1 3/4 6-11 Amendment No.135

3/4.6 CONTAINMENT SYSTEMS

BASES 1 3/4.6.1 PRIMARY CONTAINMENT t

3/4.6.1.1 CONTAINMENT INTEGRITY I

Primary CONTAINMENT INTEGRITY ensures that the release ofradioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restnc-1 tion, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE

, The limitations on containment leakage rates (including those used in demonstrating a 30 day water seal) ensure that the total contamment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, Pp . As an added conservatism, the measured overallinte- l i grated leakage rate is further limited to less than or equal to 0.75 La during ,

i performance of the periodic test to account for possible degradation of the l containment leakage barriers between leakage tests. i l

. The surveillance testing for measuring leakage rates is consistent with l the Containment Leakage Rate Testing Program. !

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, 3/4.6.1.3 REACTOR BUILDING AIR LOCKS I The limitations on closure for the reactor building air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between airlockleakage tests.

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SUMMER-UNIT 1 B 3/4 6-1 Amendment No. , 94,-1M,

CONTAINMENT SYSTEMS

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i BASES ,

3/4.6.1.7 REACTOR BUILDING VENTILATION SYSTEM ;

! The 36-inch containment purge supply and exhaust isolation valves are

required to be closed during plant operation since these valves have not been i i demonstrated capable of closing during a LOCA or steam line break accident. ;

i Maintaining these valves closed during plant operations ensures that excessive

{ quantities of radioactive materials will not be released via the containment i i purge system. To provide assurance that the 36-inch valves cannot be inadvert- i

ently opened, they are sealed closed in accordance with the Standard Review l Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, !

j or prevent power from being supplied to the valve operator. l j The use of the containment purge lines is restricted to the 6 inch purge l i

supply and exhaust isolation valves since unlike the 36 inch valves the 6 inch i

! . valves will close during a LOCA or steam line break accident and therefore the

site boundary dose guidelines of10 CFR 100 would not be exceeded in the event i

of an accident during purging operations.'

i l Periodic leakage integrity tests .for purge supply and exhaust isolation l valves with resilient material seals will be performed in accordance with the j Containment Leakage Rate Testing Program. l i

f 3/4.6.2. DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 REACTOR BUILDING SPRAY SYSTEM l The OPERABILITY of the reactor building spray system ensures that reactor i building depressurization and cooling capability will be available in the l event of a steam line break. The pressure reduction and resultant lower l containment leakage rate are consistent with the assumptions used in the

! accident analyses.

l l The reactor building spray system and the reactor building cooling system

are redundant to each other in providing post accident cooling of the reactor 4 building atmosphere. However, the reactor building spray system also provides a mechanism for removing iodine from the reactor building atmosphere and j therefore the time requirements for restoring an inoperable spray system to j OPERABLE status have been maintained consistent with that assigned other I inoperable ESF equipment.

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SUMMER-UNIT 1 B 3/4 6-3 Amendment No.135 l

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)I ADMINISTRATIVE CONTRO1E j l

f. Radiological Environmental Monitorine Program )

A program shall be provided to monitor the radiation and radionuclides j in the environs of the plant. The program shall piovide (1) representative measures of radioactivity in the highest potential exposure pathways, j and (2) verification of the accuracy of the effluent monitoring program i and modeling of environmental exposure pathways. The program shall ;

(1) be contained in the ODCM (2) conform to the guidance of Appendix I '

to 10 CFR Part 50, and (3) inciude 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; ,

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 i 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 4 measurements of radioactive materials in environmental sample >

matrices are performed as part of the quality assurance program for environmentalmonitormg.

g. Containment Leakare Rate Testing Program .

A program shall be established to implement leakage rate testing of the containment system as required by 10 CFR 50.54(o) and 10 CFR ,

50, Appendix J, Option B, as modified by approved exemptions. This arogram shall be m accordance with the pu,delines contained in hgulatory Guide 1.163," Performance-f ased Contamment Leak-Test ,

Program", dated September 1995; NEI 94-01, " Industry Guideline for Performance-Based Op" tion of 10 CFR 50, Appendix J", Revision 0; ANSI /ANS-56.8-1994, ContainmentSystem Leakage Testing Requirements"; as modified by approved exceptions. l l

The peak calculated containment internal pressure for the design basis loss ofcoolant accident, Pa, is 45.1 psig. !

l The maximum allowable containr;ent leakage rate, La, at Pa, is 0.20 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Leakage rate acceptance criteria are: l

1) Containment overallleakage rate acceptance criterion is s 1.0 La.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the combined Type B and Type C tests, and s 0.75 La for Type A tests; SUMMER-UNIT 1 6-12b Amendment No.M4,4W,4M, 135

I ADMINISTRATIVE CONTROLS

g. Containment Leakare Rate Testing Program (Continued) 1

2) Air lock testing acceptance criteria are:

a. Overall air lock leakage rate is s 0.10 La when tested at a Pa.

b. For each door, leakage rate is s 0.01 Lawhen pressurized to 2 8.0 psig for atleast 3 minutes.

The provisions of Specification 4.0.2 do not aaply to the test frequencies specified in the Containment Leakage Rate "esting Program. i The provisions ofSpecification 4.0.3 are applicable to the Containment Leakage Rate TestmgProgram.

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l SUMMER-UNITI 6-12c Amendment No.135

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ML20128G289

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