ML18153A335

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Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR
ML18153A335
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/24/1998
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153A334 List:
References
NUDOCS 9809290256
Download: ML18153A335 (16)
v • d • e


Text

' l Attachment 2 Proposed Supplemental Technical Specifications Change

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PDR ADOCK 05000280 p PDR

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Deleted.

TS 6.1-8

10. Deleted.
11. Review of every unplanned onsite release of radioactive material to the environs exceeding the limits of Specification 3.11, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear Operations and to the Management Safety Review Committee.
12. Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
13. Review of the Fire Protection Program and implementing procedures and shall submit recommended Program changes to the designated offsite management responsible for reviewing changes that pertain to Fire Protection.
g. Authority The SNSOC shall:
1. Provide written approval or disapproval of items considered under (1) through (3) above. SNSOC approval shall be certified in writing by either the Manager - Station Operations and Maintenance or the Manager -

Station Safety and Licensing.

2. Render determinations in writing with regard to whether or not each item considered under (1) through (5) above constitutes an unreviewed safety question.
3. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -

Nuclear Operations and to the Management Safety Review Committee of disagreement between SNSOC and the Site Vice President; however, the Site Vice President shall have responsibility for resolution of such disagreements pursuant to 6.1.A above.

h. Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations and to the Management Safety Review Committee.

Amendment Nos.

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D. All procedures described in Specifications 6.4.A and 6.4.B shall be followed.

TS 6.4-4 E. The facility Fire Protection Program and implementing procedures which have been established for the station shall be implemented and maintained.

F. Deleted G. In cases of emergency, operations personnel shall be authorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility. Such changes shall be documented, reviewed and approved by the Station Nuclear Safety and Operating Committee.

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Amendment Nos.

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Attachment 3 Significant Hazards Consideration Determination

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SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Virginia Electric and Power Company has reviewed the proposed Technical Specifications change against the criteria of 10 CFR 50.92 and has concluded that the change does not pose a significant safety hazards consideration as defined therein.

The proposed Technical Specifications change is administrative in nature. The change revises the review requirements for changes to the Fire Protection Program and implementing procedures and re-instates, in part, a previously deleted Technical Specification that requires the establishment, implementation and maintenance of the Fire Protection Program and implementing procedures.

The two requirements that are being incorporated into the TS are consistent with GL 88-12 guidance for relocating Fire Protection requirements in the TS to the UFSAR and supplements our original TS submittal dated January 26, 1993 (Serial No.92-727).

Since these two changes only deal with administrative requirements, neither of these two specific changes would result in a significant hazards consideration. Therefore, the operation of Surry Power Station with the proposed amendment will not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The probability of an accident is not increased as a result of this Technical Specifications change request. This is an administrative change and merely incorporates two additional requirements for ensuring that the Fire Protection Program and implementing procedures are appropriately established, implemented and maintained, and that changes to the Program and implementing procedures receive the appropriate offsite review. The consequences of an accident previously evaluated are not increased since the station will not be operated differently, and no physical modifications are being made to plant systems or components.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated.

A new or different type of accident is not being created since this TS change request is administrative. As noted above, the station will not be operated differently, and no physical modifications are being made to plant systems or components. Administrative rev1s1ons regarding the establishment, implementation and maintenance of a TS requirement for a Fire Protection Program and implementing procedures and the imposition of an offsite review for changes thereto does not create a new or different type of accident from any accident previously evaluated.

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3. Involve a significant reduction in a margin of safety.

The margin of safety as defined in the Technical Specifications is not reduced since system/component performance as assumed in the existing safety analyses is not being affected by the proposed TS change. The TS change is administrative in nature and, as such, has no effect on station operation. The Fire Protection Program is being retained and maintained in the UFSAR and station procedures.

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Attachment 4 Complete Proposed Technical Specifications Pages

'*' e when the Health Physics Coordinator for the Steam Generator Repair Program determines, based on an evaluation involving ALARA considerations, that their use will increase overall occupational radiation exposure to workers involved in the repair activities.

(c) The health physics program and procedures which have been established for the steam generator repair program shall be implemented.

(d) Progress reports shall be provided at 60 day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair. These reports will include:

(i) A summary of the occupational exposure expended to date using the format and detail of Table 5.3-1 of the report entitled "Steam Generator Repair Program."

(ii) An evaluation of the effectiveness of dose reduction techniques as specified in Chapter 6 of the report entitled "Steam Generator Repair Programs" in reducing occupational exposures.

(iii) An estimate of radioactivity released in both liquid and gaseous effluents.

(iv) An estimate of the solid radioactive waste generated during the repair effort including volume and radioactive content.

(3) Sixty days prior to fuel loading, the program for preoperational testing and startup shall be submitted for NRC review.

H. The licensee shall maintain in effect and fully implement all prov1s10ns of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d),

referred to as Surry Power Station Unit Nos. 1 and 2 Physical Security Plan, dated November 30, 1977, as revised September 25, 1978, supplemented (Chapter 10)

October 25, 1978, revised January 12, 1979, and supplemented February 16, 1979.

Surry - Unit 1 Amendment No.

I.

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

J. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "S~rry Power Station Physical Security Plan," with revisions submitted through February 24, 1988; "Surry Power Station Guard Training and Qualification Plan," with revisions submitted through May 29, 1987; and "Surry Power Station Safeguards Contingency Plan," with revisions submitted through January 9, 1987.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

K. Secondary Water Chemistry Monitoring Program The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points;
3. Identification of process sampling points;
4. Procedure for the recording and management of data;_
5. Procedures definip.g corrective actions for off contro1_point chemistry conditions; and
6. A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.

Surry - Unit 1 Amendment No.

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  • when the Health Physics Coordinator for the Steam Generator Repair Program determines, based on an evaluation involving ALARA considerations, that their use will increase overall occupational radiation exposure to workers involved in the repair activities.

(c) The health physics program and procedures which have been established for the steam generator repair program shall be implemented.

(d) Progress reports shall be provided at 60 day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair. These reports will include:

(i) A summary of the occupational exposure expended to date using the format and detail of Table 5.3-1 of the report entitled "Steam Generator Repair Program."

(ii) An evaluation of the effectiveness of dose reduction techniques as specified in Chapter 6 of the report entitled "Steam Generator Repair Programs" in reducing occupational exposures.

(iii) An estimate of radioactivity released in both liquid and gaseous effluents.

(iv) An estimate of the solid radioactive waste generated during the repair effort including volume and radioactive content.

(3) Sixty days prior to fuel loading, the program for preoperational testing and startup shall be submitted for NRC review.

H. The licensee shall maintain in effect and fully implement all prov1S1ons of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d),

referred to as Surry Power Station Unit Nos. 1 and 2 Physical Security Plan, dated November 30, 1977, as revised September 25, 1978, supplemented (Chapter 10)

October 25, 1978, revised January 12, 1979, and supplemented February 16, 1979.

Surry - Unit 2 Amendment No.

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1.

The licensee may make changes to the approved fire protection program without prior approval of the .Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

J. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p ).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Surry Power Station Physical Security Plan," with revisions submitted through February 24, 1988; "Surry Power Station Guard Training and Qualification Plan," with revisions submitted through May 29, 1987; and "Surry Power Station Safeguards Contingency Plan," with revisions submitted through January 9, 1987.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

K. Secondary Water Chemistry Monitoring Program The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

1. Identification of a sampling schedule for the critical parameters and control points for these parameters;
2. Identification of the procedures used to quantify parameters that are critical to control points; 3.* Identification ofprocess sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry conditions; and
6. A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.

Surry - Unit 2 Amendment No.

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  • . 1ECHNICAL SPECIFICATION TS ii TABLE OF CONTENTS SECTION TITLE PAGE 3.15 DELETED 3.16 EMERGENCY POWER SYSTEM TS 3.16-1 3.17 LOOP STOP VALVE OPERATION TS 3.17-1 3.18 MOVABLE INCORE INSTRUMENTATION TS 3.18-1 3.19 MAIN CONTROL ROOM BOTTLED AIR SYSTEM TS 3.19-1 3.20 SHOCK SUPPRESSORS (SNUBBERS) TS 3.20-1 3.21 DELETED 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS TS 3.22-1 3.23 CONTROLANDRELAYROOMVENTILATION SUPPLYFILTER TS 3.23-1 TRAINS 4.0 SURVEILLANCE REQUIREMENTS TS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW TS 4.1-1 4.2 AUGMENTED INSPECTIONS TS 4.2-1 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE TESTS TS 4.3-1 4.4 CONTAINMENT TESTS TS 4.4-1 4.5 -SPRAY-SYSTEMS TESTS TS 4.5-1 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING TS 4.6-1 4.7 MAIN STEAM LINE TRIP VALVES TS 4.7-1 4.8 AUXILIARY FEEDWATER SYSTEM TS 4.8-1 4.9 RADIOACTIVE GAS STORAGE MONITORING SYSTEM TS 4.9-1 4.10 REACTIVITY ANOMALIES TS 4.10-1 4.11 SAFETY INJECTION SYSTEM TESTS TS 4.11-1 4.12 VENTILATION FILTER TESTS TS 4.12-1 4.13 DELETED 4.14 .DELETED Amendment Nos.

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  • TECHNICAL SPECIFICATION TS iii TABLE OF CONTENTS SECTION TITLE PAGE 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH TS 4.15-1 ENERGY LINES OUTSIDE OF CONTAINMENT 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE TS 4.16-1 MATERIALS SOURCES 4.17 SHOCK SUPPRESSORS (SNUBBERS) TS 4.17-1 4.18 DELETED 4.19 STEAM GENERATOR INSERVICE INSPECTION TS 4.19-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM TS 4.20-1 5.0 DESIGNFEATURES TS 5.1-1 5.1 SITE TS 5.1-1 5.2 CONTAINMENT TS 5.2-1 5.3 REACTOR TS 5.3-1 5.4 FUEL STORAGE TS 5.4-1 6.0 ADMINISTRATIVE CONTROLS TS 6.1-1 6.1 ORGANIZATION, SAFETY AND OPERATION REVIEW TS 6.1-1 6.2 GENERAL NOTIFICATION AND REPORTING REQUIREMENTS TS 6.2-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED TS 6.3-1 6.4 UNIT OPERATING PROCEDURES TS 6.4-1 6.5 STATION OPERATING RECORDS TS 6.5-1 6.6 STATION REPORTING REQUIREMENTS TS 6.6-1 6.7 ENVIRONMENTAL QUALIFICATIONS TS 6.7-1 6.8 PROCESS CONTROL PROGRAM AND OFFSITE DOSE TS 6.8-1 CALCULATION MANUAL Amendment Nos.

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7. Deleted.

TS 6.1-3 8.' Deleted.

9. The health physics technician requirement of Specification 6.1.B.5 may not be met for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate an unexpected absence provided immediate action is taken to fill the required position.
10. Procedures will be established to insure that NRC policy statement guidelines regarding working hours established for employees are followed. In addition, procedures will provide for documentation of authorized deviations from those guidelines and that the documentation is available for NRC review.

Amendment Nos.

9.

Deleted.

TS 6.1-8

10. Deleted.
11. Review of every unplanned onsite release of radioactive material to the environs exceeding the limits of Specification 3 .11, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear Operations and to the Management Safety Review Committee.
12. Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
13. Review of the Fire Protection Program and implementing procedures and shall submit recommended Program changes to the designated offsite management responsible for reviewing changes that pertain to Fire Protection.
g. Authority The SNSOC shall:
1. Provide written approval or disapproval of items considered under ( 1) through (3) above. SNSOC approval shall be certified in writing by either the Manager - Station Operations and Maintenance or the Manager -

Station Safety and Licensing.

2. Render determinations in writing with regard to whether or not each item considered under (1) through (5) above constitutes an unreviewed safety question.
3. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -

Nuclear Operations and to the Management Safety Review Committee of disagreement between SNSOC and the Site Vice President; however, the Site Vice President shall have responsibility for resolution of such disagreements pursuant to 6.1.A above.

h. Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations and to the Management Safety Review Committee.

Amendment Nos.

D. All procedures described in Specifications 6.4.A and 6.4.B shall be followed.

TS 6.4-4 E. The facility Fire Protection Program and implementing procedures which have been established for the station shall be implemented and maintained.

F. Deleted G. In cases of emergency, operations personnel shall be authorized to depart from approved procedures where necessary to prevent injury to personnel or damage to the facility. Such changes shall be documented, reviewed and approved by the Station Nuclear Safety and Operating Committee.

Amendment Nos.

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