Similar Documents at Surry |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request 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Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re 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Which Presents reload- Specific Limits for Key Core Operating Parameters ML18153D3811993-07-0202 July 1993 Proposed TS Table 4.2-1 Re Miscellaneous Insps & Sensitized Stainless Steel Exams ML18153D3331993-05-0606 May 1993 Proposed Tech Specs Supporting Operation of Unit 2 w/100 Psi Reduction in RCS Nominal Operating Pressure Through End of Operating Cycle 12 1999-08-23
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18152B3591999-08-23023 August 1999 Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section ML18151A6641999-08-0606 August 1999 Rev 0 to Surry Unit 2 Cycle 16 Startup Physics Tests Rept. ML18152B6591999-04-28028 April 1999 Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol ML18152A2131999-02-16016 February 1999 Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B5451999-02-16016 February 1999 Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18151A5511999-02-10010 February 1999 to NE-1187, Surry Unit 1,Cycle 16 Startup Physics Tests Rept. ML18152B6151998-11-0404 November 1998 Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings ML18153A3351998-09-24024 September 1998 Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR ML18153A3311998-09-24024 September 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML18152B7551998-06-19019 June 1998 Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML20249B9911998-05-0606 May 1998 Analysis of Capsule X Virginia Power Surry Unit 1 Reactor Vessel Matl Surveillance Program. W/Evaluation of Surry Unit 1 Surveillance Capsule X Results & Response to NRC RAI Re GL 92-01,rev 1,suppl 1 ML18151A1931998-05-0404 May 1998 Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program. ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20199B0711998-01-0505 January 1998 Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept ML18153A3481997-12-18018 December 1997 Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431 ML18150A4661997-12-16016 December 1997 ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2 ML18153A3941997-11-0505 November 1997 Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel ML18153A1761997-11-0505 November 1997 Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers ML18150A4641997-10-27027 October 1997 Risk-Informed ISI (RI-ISI) Pilot Program Submittal. ML18151A3911997-10-16016 October 1997 Rev 8 to VPAP-2103, Odcm. ML18151A7231997-08-0707 August 1997 Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products. ML20210J5031997-07-31031 July 1997 Rev 0 to NE-1132, Surry Unit 1,Cycle 15 Startup Physics Tests Rept ML18150A4441997-06-0909 June 1997 Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003. ML18153A5231997-04-24024 April 1997 Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept ML18153A5031997-03-18018 March 1997 Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37 ML18153A4921997-02-0303 February 1997 Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref ML18153A6351996-11-26026 November 1996 Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06 ML18153A0671996-09-12012 September 1996 Proposed Tech Specs Re Relocation of Fire Protection Requirements ML18151A9761996-08-13013 August 1996 Cycle 14 Startup Physics Test Rept. W/960830 Ltr ML20134J9861996-07-30030 July 1996 /Unit 2 Fuel Assembly Insp Program ML18152A4701996-06-13013 June 1996 Cycle 13 Control Rod Performance Test Results. ML18153A6901996-04-15015 April 1996 Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements ML18153A5391996-03-21021 March 1996 Proposed Tech Specs Re Charcoal Filter Testing Clarification ML18153A5271996-03-14014 March 1996 Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML18153A5801996-01-30030 January 1996 Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling ML18152A0571995-12-20020 December 1995 Startup Physics Test Rept,Surry Unit 1,Cycle 14. W/960111 Ltr ML18153A6761995-11-20020 November 1995 Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing ML18151A6421995-08-0101 August 1995 Change 3 to Rev 0 to Third Interval IST Program ML18153A7141995-07-20020 July 1995 Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6991995-07-14014 July 1995 Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation ML18153A8371995-06-0808 June 1995 Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license ML20083C9951995-05-0808 May 1995 Rev 0 to Surry Unit 2,Cycle 13 Startup Physics Tests Rept ML18153B2301995-02-14014 February 1995 Proposed Tech Specs Re App J Testing Requirements ML18153B2131995-01-24024 January 1995 Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1621994-11-29029 November 1994 Proposed Tech Specs Implementing Zirlo Fuel Cladding ML18153B1581994-11-22022 November 1994 Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1501994-11-10010 November 1994 Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0941994-10-11011 October 1994 Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers ML18152A5061994-09-0606 September 1994 Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities ML18152A1191994-08-30030 August 1994 Proposed Tech Specs to Accomodate Core Uprating 1999-08-06
[Table view] |
Text
- e ATTACHMENT 1 Proposed Technical Specification Change
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Discussion Technical Specification (TS) 6.4.B addresses procedures for personnel radiation protection consistent with the requirements of 10 CFR 20. Specifically, TS 6.4.B.1 contains various provisions which serve as alternatives to the requirements of 10 CFR 20.203(c)(2), dealing with controls to the entrance or access point of high radiation areas. Alternatives to 10 CFR 20.203(c)(2) are allowed under 10 CFR 20.203(c)(5).
The present Section 6.4.B is an "originally issued" portion of Technical Specifications.
Based on a request dated April 1, 1971, for exemption from the provisions of 10 CFR 20.203(c)(2), it appears that the present TS 6.4.B was intended to function as a customized version of the subsequent Standard Technical Specifications (STS),
Section 6.12. Since this exemption request was made prior to the issuance of the Operating License, we surmise that the elements of TS 6.4.B were formed as compensatory/clarifying specifications during Technical Specification development for the Operating License.
Included in TS 6.4.B is a requirement to maintain a "buddy system" for entrance into radiation areas in excess of 1 R/hr. For this requirement, one worker maintains positive control of the locked gate regardless of whether it is open or closed at the time while the other worker (his "buddy") performs the necessary work. The* two individuals are required to maintain continuous communication by visual or verbal means during this period. Due to this requirement, two individuals are subject to radiation exposure, regardless of whether both are required to accomplish the work.
In our review of the historical record, we can find no technical bases or discussion which justifies or directs the inclusion of the "buddy system" into Technical Specifications. With respect to the regulatory and radiation protection standards of today, the "buddy system" requirement of TS 6.4.B.1.f is inconsistent with STS and contrary to common ALARA practices. Deletion of TS 6.4.B.1.f will result in a significant reduction in man-rem exposure (approximately 9.6 man-rem per year). In addition, the proposed TS 6.4.B has been rewritten using a new format. The new format conforms to that used in NUREG-0452, Revision 4, "Standard Technical Specifications for Westinghouse Pressurized Water Reactors." In addition, the content of TS 6.4.B has been revised to be consistent with the corresponding Technical Specifications for the North Anna Power Station. A summary of the changes being requested is as follows:
- 1. Surry requirements specified by TS 6.4.B.1.c are being deleted. This section duplicates requirements contained in 10 CFR 20.201 and is therefore, not necessary.
- 2. Personnel indoctrination required* by TS 6.4.B.1.d is being deleted. This section duplicates requirements contained in 10 CFR 19.12.
- 3. The "buddy system" of TS 6.4.B.1.f is being deleted. The "buddy system" results in unnecessary personnel exposures and is not consistent with maintaining exposures As Low As Reasonably Achievable (ALARA).
_J
e
- 4. The requirement for fencing of buildings contained in TS 6.4.B.1.h is being deleted. Physical protection of buildings and materials is required by 10 CFR 73.
- 5. Generic terminology has been used to define the responsible individual for health physics and radiation protection to avoid future conflicts due to title changes.
TS 6.4-1 6.4 UNIT OPERATING PROCEDURES Specification A. Detailed written procedures with appropriate check-off lists and instructions shall be provided for the following conditions:
- 1. Normal startup, operation, and shutdown of a unit, and of all systems and components involving nuclear safety o_f the station.
- 2. Calibration and testing of instruments, components, and systems involving nuclear safety of the station.
- 3. Actions to be taken for specific and foreseen malfunctions of systems or components including alarms, primary system leaks and abnormal reactivity changes.
- 4. Release of radioactive effluents.
- 5. Emergency conditions involving potential or actual release of radioactivity.
- 6. Emergency conditions involving violation of industrial security.
- 7. Preventive or corrective maintenance operations which would have an effect on the safety of the reactor.
- 8. Refueling operations.
B. Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and* adhered 'to for all operations involving personnel radiation exposure.
e TS 6.4-2
- 1. In lieu of the "control device" or "alarm signal" required by paragraph 20.230(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas vvith this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
- c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by Health Physics in the RWP.
- Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved plant radiation protection procedures for entry into high radiation areas.
TS 6.4-3
- 2. The requirements of 6.4.B.1 above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the senior station individual assigned the responsibility for health physics and radiation protection.
- 3. Written procedures shall be established, implemented, and maintained covering the activities referenced below:
- a. Process Control Program implementation.
- b. Offsite Dose Calculation Manual implementation.
C. All procedures described in 6.4.A and 6.4.B, and changes thereto, shall be reviewed and approved by the Station Nuclear Safety and Operating Committee prior to implementation.
ATTACHMENT 2 Significant Hazards Consideration Determination
e Significant Hazards Consideration The requested change to TS 6.4.B does not represent a significant hazard as defined by 10 CFR 50.92.
- 1. No significant increase in the probability or consequences of an accident previously evaluated is created. The change to TS 6.4.B revises the TS format, removes TS requirements that are duplicated in other 1o CFR sections, and deletes the use of the "buddy system" for entering areas with radiation levels in excess of 1 R/hr. Thus, the only significant change to TS 6.4.B is to remove the "buddy system" when accessing certain high radiation areas. This change does not alter the facility, its equipment, or procedures affecting equipment operation and, therefore, has no effect on the probability or consequences of any accident.
- 2. No possibility of a new or different kind of accident from any accident previously evaluated is created. The TS change only changes the access procedures for entering areas with radiation levels in excess of 1 R/hr. As noted before, the proposed changes do not make any change to the facility or plant operation.
- 3. No significant reduction in a margin of safety is involved. The revised TS provides access control for areas with radiation levels in excess of 1 R/hr by requiring _a locked door with the keys under administrative control of the Shift Supervisor on duty and/or the senior station individual assigned responsibility for health physics and radiation protection. The TS also requires the issuance of a Radiation Work Permit for access,, except for Health Physics personnel during the performance of their assigned radiation protection duties. These controls comply with the access control alternatives specified in 10 CFR 20.203(c)(2)(iii).