Text

Amends 196 & 177 to Licenses NPF-4 & NPF-196,respectively, Revising TS Re Use of performance-based Containment Leakage Rate Testing
	ML20097F341
Person / Time
Site:	North Anna
Issue date:	02/09/1996
From:	; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20097F345	List: ML20097F341; ML20097F351;
References
	NUDOCS 9602160024
	Download: ML20097F341 (21)
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[

UNITED STATES i

B NUCLEAR REGULATORY COMMISSION A...../

WASHINGTON, D.C. 2050HOM VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.196 License No. NPF-4 1.

The Nuclear Regulatory Commission (the Commission) has fou'd that:

n A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated November 20, 1995 as supplemented January 23, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as' amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in contormity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

'There is reasonable assurance (1) 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 Part 51 of the Commission's regulations and all applicable requirer nts have been satisfied.

i h

P y

i j l I

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as l

revised through Amendment No.196, are hereby incorporated in the.

license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NU LEAR REGULATORY COMMISSION-Auf/

David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

\\

Date of Issuance:

February 9,1996 l

)

1

ATTACHMENT TO LICENSE AMENDMENT NO. 196 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Paaes Insert Paaes j

3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-9 3/4 6-9 6-22 6-22 O

t 1

i 3L4.6 CONTAINMENT SYSTEMS 3/4.6.1 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 r

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

i SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

At least once per 31 days by verifying that all penetrations

not capable of being l

a.

closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves, secured in their positions, except for valves that am open under administrative control as permitted by Specification 3.6.3.1.

b.

By verifying that each containment air lock is OPERABLE per Specification i

3.6.1.3.

After each closing of the equipment hatch, by leak rate testing the equipment hatch c.

j seals, with gas at P., greater than or equal to 44.1 psig. Results shall be evaluated j

against the criteria of Specification 3.6.1.2.b as required by 10 CFR 50, Appendix J Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995.

d. '

Each time containment integrity is established after vacuum has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.

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

NORTH ANNA - UNIT 1 3/4 6 1 Amendment No. '!5.

i

CONTAINMENT SYSTEMS CONTAINMENT LFAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

An overall integrated leakage rate ofless than or equal to L, O. percent by weight a.

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at the calculated peak containment pressure P.,

greater than or equal to 44.1 psig.

b.

A combined leakage rate of less than or equal to 0.60 L, for all pencJations and valves subject to Type B and C tests, when pressurized to P., greater than or equal j

to 44.1 psig.

APPLICABILITY:

MODES 1,2,3, and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., restore the overall integrated leakage rate to less than 0.75 L, and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 L, prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment and containment penetrations shall be tested by performing leakage rate testing as required by 10 CFR 50, Appendix J. Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

r i

NORTH ANNA-UNIT 1 3/4 6-2 Amendment No. g, !^*, ' '^

i

%,- -. --+ _

This Page Intentionally Left Blank NORTH ANNA - UNIT 1 3/4 6-3 Amendment No. !10, l" l '-

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

Both doors closed except when the air lock is being used for normal transit entry a.

and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 0.05 L, at P, greater than or equal to 44.1 psig.

APPLICABILITY:

MODES 1,2,3 and 4.

ACTION:

With one containment air lock door inoperable:

{

a.

1.

Maintain at least the OPERABLE air lock door closed and either restore the i

inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.+

i 2.

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

3.

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 .

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With a containment air lock inoperable, except as the result of an inoperable airlock door, maintain 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 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 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

By performing leakage rate testing as required by 10 CFR 50, Appendix J. Option a.

B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

b.

At least once per refueling outage by verifying that only one door in each air lock can be opened at a time.

Entry to repair the inner air lock door, ifinoperable, is allowed.

+

NORTH ANNA - UNIT 1 Et 6-t Amendment No. " ' 'a 1"

m.

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL-INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.1.

APPLICABTI ITY:

MODES 1,2,3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STAN'DBY 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 4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate shall be determined by performing visual examinations as required by 10 CFR 50, Appendix J. Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

NORTH ANNA - UNIT I 3/46-9 Amendment No

1 CONTAINMENT SYSTEMS

~

3/4.6.2 DEPRESSU_RIZATION AND COOLING SYSTEMS CONTAINMENT QUENCH SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment quench spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one containment quer.ch spray subsystem inoperable, restore the in-operable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAND 8Y 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 l

4.6.2.1 Each containment quench spray subsystem shall be demonstrated OPERABLE:

a.

- At least once per 31 days by:

1.

Verifying)that each valve (manual, power operated or automatic in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.

2.

Verifying the temperature of the borated water in the refueling water storage tank is within the limits shown on Figure 3.6-1.

b.

Verifying that on recirculation flow, each pump develops a discharge pressure of > 123 psig when tested pursuant to Specification 4.0.5.

T c.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a containment high-high signal.

2.

Verifying that each spray pump starts automatically on a containment high-high signal.

NORTH ANNA-UNIT 1 3/4 6-10

ADMINISTRATIVE CONTROLS r.

Deleted I

ilQ RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. ALL REPORTABLE EVENTS and Special Reports.

d. Records of surveillance ac:ivities, inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to Operating Procedures.

f. Records of radioactive shipments.

g. Records of sealed source leak tests and results.

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

i. Records of the Station Emergency Plan and implementing procedures audits.

j. Records of the Station Security Plan and implementation procedures audits.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

j NORTH ANNA - UNIT I

-6 22-Amendment No. 44. '

i o

= _.. -

_~

Sftroy UNITED STATES y

^

NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20006 0001

%*****/

VIRGINIA ELECTRIC AND POWER COMPANY OLO DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No. NPF-7 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated November 20, 1995 as supplemented January 23, 1996, complies with the standards and requirements of the Atomic Energy Act of.1954, as amended (the Act), and the 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 Comission; 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 Comission'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 of the Commission's regulations and all applicable requirements have been satisfied.

1

.. 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 177..are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NU LEAR REGULATORY COMMISSION

/

David B. Matthews, Director Project Directorate I1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 9,1996

ATTACHMENT TO LICENSE AMENDMENT NO.177 TO FACILITY OPERATING LICENSE N0. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Remove Paaes-Insert Paaes 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-9 3/4 6-9 6-21 6-21 1

Jfig CONTAINMENT SYSTEMS 3/411 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 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 .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

At least once per 31 days by verifying that all penetrations

not capable of being l

a.

closed by OPERABLE containment automatic isolation valves and required to be 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 I

administrative control as permitted by Specification 3.6.3.1.

.b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

After each closing of the equipment hatch, by leak rate testing the equipment hatch c.

seals, with gas at P., greater than or equal to 44.1 psig. Results shall be evaluated against the criteria of Specification 3.6.1.2.b as required by 10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995.

d.

Each time containment integrity is established after vacutim has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.

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

NORTH ANNA - UNIT 2 3/46-1 Amendment No. aa,151, M2.1 "

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

An overall integrated leakage rate ofless than or equal to L,0.1 percent by weight a.

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at the calculated peak containment pressure P.,

greater than or equal to 44.1 psig.

b.

A combined leakage rate of less than or equal to 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P., greater than or equal to 44.I psig.

APPLICABILITY:

MODES 1,2,3, and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., restore the overall integrated leakage rate to less than 0.75 L and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 L prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment and containment penetrations shall be tested by performing leakage rate testMg as required by 10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

NORTH ANNA - UNIT 2 3/4 6-2 Amendment No. 92, 9', M. " '

This Page Intentionally Left Blank l

l NORTH ANNA - UNIT 2 3/4 6-3 Amendment No. %-654. ' ' '

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

Both doors closed except when the air lock is being used for normal transit entry a.

and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 0.05 L, at P. greater than or equal to 44.1 psig.

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

ACTION:

With one containment air lock door inoperable:

a.

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE airlock 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 verified to be locked closed at least once per 31 days.

3.

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 .

4.

The provisions of Specification 3.0.4 are not applicable.

b.

With a containment air lock inoperable, except as the result of an inoperable rir lock door, maintain 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 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 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

By performing leakage rate testing as required by 10 CFR 50, Appendix.I, Option a.

B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

i b.

At least once per refueling outage by verifying that only one door in each air lock can be opened at a time.

Entry to repair the inner air lock door, if inoperable, is allowed.

+

NORTH ANNA - UNIT 2 3/4 6-4 Amendment No. 6L-06.177 i

l l

i 1

This Page Intentionally Left Blank i

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j

. NORTH ANNA - UNIT 2 3/46-5 Amendment No. 9A

1 CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal air partial pressure shall be maintained greater than or equal to 9.0 psia and within the acceptable operation on Figure 3.6-1.

I APPLICA8ILITY:

M00ES 1, 2, 3 and 4.

)

i ACTION:

With the containment internal air partial pressure less than 9.0 psia or above j

the appitcable limit shown on Figure 3.6-1, restore the internal air partial i

pressure to within the limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next S hours 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. 4 The primary containment internal air partial pressure shall be deter-mined to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

j N

o I

NORTH ANNA - UNIT 2 3/4 6-6 Amendment No. 96 OEC 141998

,4_4-1__

^

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.1.

APPLICABILITY:

MODES 1,2,3 and 4.

ACTION:

With the stmetural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANi)BY 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 4.6.1.6.1 containment Surfaces The structurd integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate shall be determined by performing visual examinations as required by 10 CFR 50, Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September 1995. The provisions of Specification 4.0.2 are not applicable.

l NORTH ANNA - UNIT 2 3/4 6-9 Amendrr.:nt No. 47. W

?

s ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:

Inservice Inspection Reviews, Specification 4.0.5, shall be reported within 90 days a.

of completion.

b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.

c. Deleted.

d. RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1, Table 3.3-6, Action 35.

e. Deleted.

f. LOW-TEMPERATURE OVERPRESSURE PROTECTION. Specification 3.4.9.3.

g. EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3.

h. SE'ITLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.

i. GROUND WATER LEVEL - SERVICE WATER RESERVOIR. Specification 3.7.13.

j. Deleted.

k. Deleted.

1.

RADIOACTIVE EFFLUENTS. As required by the ODCM.

m. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.

n. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.

o. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specifhtion 4.4.10. For any abnormal degradation of the structural integrity of the rear.or vessel or the Reactor Coolant System pressure boundary detected during th' performance of Specification 4.4.10, an initial report shall be submitted wid.in 10 days after detection and a detailed report submitted within 90 days arter the completion of Specification 4.4.10.

p. Deleted.

l NORTH ANNA - UNIT 2 6-21 Amendment No. 3 !, ". 83, ^^

ii4 m tan

v t e Letter Sequence Request
TAC:M94303, (Open)
Initiation Request Acceptance... Administration Questions Answers Results Approval... Other: ML20116A883
MONTHYEAR1996-02-09 [Table View]

ML20097F341

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