ML14112A073

Proposed License Amendment Request Relocation of Augmented Inspection Requirements from TS 4.2 and TS 4.15 to Technical Requirements Manual

ML14112A073
Person / Time
Site:	Surry
Issue date:	04/11/2014
From:	Mark D. Sartain Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
14-158
Download: ML14112A073 (34)

Text

VIRGINIA ELECTRIC AND POWER COMPANY PRICHMOND, VIRGINIA 23261 April 11, 2014 10 CFR 50.90 U. S. Nuclear Regulatory Commission Serial No.: 14-158 Attention: Document Control Desk SPS/LIC-CGL: R1 Washington, DC 20555-0001 Docket Nos.: 50-280/281 License Nos.: DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 PROPOSED LICENSE AMENDMENT REQUEST RELOCATION OF AUGMENTED INSPECTION REQUIREMENTS FROM TS 4.2 AND TS 4.15 TO TECHNICAL REQUIREMENTS MANUAL Pursuant to 10CFR50.90, Virginia Electric and Power Company (Dominion) is submitting a license amendment request to revise the Surry Units 1 and 2 Technical Specifications (TS). Specifically, TS 4.2, "Augmented Inspections," and TS4.15, "Augmented Inservice Inspection Program for High Energy Lines Outside of Containment," will be relocated to the Surry Technical Requirements Manual (TRM). In addition, TS 6.4.U, "Augmented Inspections and Examinations," will be added to the Administrative Controls Section 6.4, "Unit Operating Procedures and Programs." The proposed relocation of the TS 4.2 and TS 4.15 requirements to the TRM is appropriate since these requirements do not satisfy the categories and criteria of 10CFR50.36(c) for inclusion in the TS. Along with the relocation of the TS 4.2 and TS 4.15 requirements to the TRM, the Bases for TS 4.2 and TS 4.15 are also being relocated to the TRM. provides a discussion of the proposed change. The marked-up and proposed pages for the TS and TS Bases are provided in Attachments 2 and 3, respectively. The TS Bases changes are provided for NRC information only.

We have evaluated the proposed amendment and have determined that it does not involve a significant hazards consideration as defined in 10CFR50.92. The basis for this determination is included in Attachment 1. We have also determined that operation with the proposed change will not result in any significant increase in the amount of effluents that may be released offsite or any significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed amendment is eligible for categorical exclusion from an environmental assessment as set forth in 10CRF51.22(c)(9). Pursuant to 10CFR51.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed change. The proposed TS change has been reviewed and approved by the Facility Safety Review Committee.

4oDl

Serial No.14-158 Docket Nos. 50-280/281 Page 2 of 3 Dominion requests approval of the proposed change by April 30, 2015 with a 60-day implementation period.

Should you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.

Respectfully, Mark D. Sartain Vice President - Nuclear Engineering Commitments contained in this letter: None Attachments:

1. Discussion of Change

2. Marked-up Technical Specifications and Bases Pages

3. Proposed Technical Specifications and Bases Pages COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mr. Mark D. Sartain, who is Vice President -

Nuclear Engineering, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this tI*" day of ,2014.

My Commission Expires: "( 3 2v t.

2,(

.. WANDA 0. CRAFT ..

I Notary Public N P Commonwealth of Virginia Notary Public yosReg. # 7520495 MyComrnission Expires January 31, 20IE

Serial No.14-158 Docket Nos. 50-280/281 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - 7 th floor 109 Governor Street Suite 730 Richmond, VA 23219 Ms. M. C. Barillas NRC Project Manager - Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.14-158 Docket Nos. 50-280/281 Attachment I DISCUSSION OF CHANGE Virginia Electric and Power Company (Dominion)

Surry Station Units 1 and 2

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 1 of 7 DISCUSSION OF CHANGE

1.0 INTRODUCTION

In accordance with the provisions of 10CFR50.90, Virginia Electric and Power Company (Dominion) is submitting a license amendment request to revise the Surry Units 1 and 2 Technical Specifications (TS). Specifically, TS 4.2, "Augmented Inspections," and TS 4.15, "Augmented Inservice Inspection Program for High Energy Lines Outside of Containment," will be relocated to the Surry Technical Requirements Manual (TRM). In addition, TS 6.4.U, "Augmented Inspections and Examinations," will be added to the Administrative Controls Section 6.4, "Unit Operating Procedures and Programs." The proposed relocation of the TS 4.2 and TS 4.15 requirements to the TRM is appropriate since these requirements do not satisfy the categories and criteria of 10CFR50.36(c) for inclusion in the TS. Along with the relocation of the TS 4.2 and TS 4.15 requirements to the TRM, the Bases for TS 4.2 and TS 4.15 are also being relocated to the TRM. The TS Bases changes are provided to the NRC for information.

2.0 PROPOSED CHANGE

The proposed TS revisions are summarized below:

• TS 4.2 and the TS 4.2 Bases will be relocated in their entirety to the Surry TRM.

" TS 4.15 and the TS 4.15 Basis will be relocated in their entirety to the Surry TRM.

" TS 6.4.U, "Augmented Inspections and Examinations," will be added to the Administrative Controls Section 6.4, "Unit Operating Procedures and Programs," to provide a description of the augmented inspections and examinations being relocated to the Surry TRM.

Marked-up TS and TS Bases pages and typed proposed TS pages are provided in Attachments 2 and 3, respectively.

3.0 BACKGROUND

TS 4.2 - Augmented Inspections TS 4.2 provides requirements for inservice inspections which augment those required by ASME Section XI. These requirements provide additional assurance of continued integrity of important components. The current TS 4.2 augmented inspections were incorporated into the Surry TS by Amendments 128/128, issued by an NRC letter dated May 24, 1989. Amendments 128/128 removed obsolete inservice inspection/testing

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 2 of 7 requirements and replaced them with more up-to-date NRC-approved requirements specified in 10CFR50.55a(g). The augmented inspections currently in TS 4.2 address the low head safety injection piping in the valve pit, the reactor coolant pump flywheel, the low pressure turbine blades, and sensitized stainless steel. Sensitized stainless steel was discussed in the Surry Safety Evaluation Report and sensitized stainless steel inspection requirements were included in the original Surry TS in response to an Atomic Safety and Licensing Board (ASLB) hearing decision dated April 26, 1972. The addition of TS 6.4.U, "Augmented Inspections," which provides a description of the augmented inspections and examinations being relocated to the TRM, including sensitized stainless steel, continues to meet the conclusions stated in the ASLB decision.

TS 4.15 - Augmented Inservice Inspection Program for High Energy Lines Outside of Containment TS 4.15 provides an augmented inservice inspection program for high energy lines outside of containment. These requirements apply to welds in piping systems or portions of piping systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed specifically to cope with such ruptures. These augmented inservice inspections provide assurance of the continued integrity of the piping systems over their service life. These requirements were incorporated into the Surry TS by Change No.

13, issued by an NRC letter dated September 21, 1973. These requirements resulted from the NRC review of the Surry analysis of postulated high energy line breaks outside of containment and apply to welds in the main steam and main feedwater lines in the main steam valve house of both units.

4.0 REGULATORY/TECHNICAL ANALYSIS 4.1 Comparison to 10CFR50.36 Categories and Criteria for Inclusion in TS The relocation of the TS 4.2 and TS 4.15 augmented inspection requirements to the TRM is appropriate because the requirements do not satisfy the 10CFR50.36 categories and criteria for inclusion of information in TS.

10CFR50.36(c) states that technical specifications will include items in the following categories:

(1) Safety limits, limiting safety system settings, and limiting control settings.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not safety limits or limiting safety system settings related to protection of the nuclear reactor.

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 3 of 7 Note that limiting control settings apply to fuel reprocessing plants, not to nuclear reactors.

(2) Limiting conditionsfor operation.

(A) Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

(B) Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

(C) Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

(D) Criterion4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not limiting conditions for operation for installed instrumentation, a process variable/design feature/operating restriction, a primary success path structure, system, or component (SSC), or an SSC shown to be significant to public health and safety.

(3) Surveillance requirements.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not surveillance requirements (relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met) that are required to be included in the TS. The augmented inspections are performed in addition to required ASME Code Section Xl inspections/examinations and will continue to be performed as required by the TRM.

(4) Design features.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not facility design features, such as materials of construction and geometric arrangements, that could have a significant effect on safety.

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 4 of 7 (5) Administrative controls.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not administrative controls relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure safe operation.

(6) Decommissioning.

(7) Initial notification.

(8) Written reports.

The TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment are not related to nuclear power plant decommissioning, initial notification reports, or written reports in accordance with 10CFR50.73 or Special Reports.

As discussed above, the TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment do not satisfy the 10CFR50.36(c) categories and criteria for inclusion of information in TS. Thus, relocation of the TS 4.2 augmented inspections and the TS 4.15 augmented inservice inspection program for high energy lines outside of containment to the TRM is appropriate.

4.2 No Significant Hazards Consideration The NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10CFR50.92(c). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: 1) involve a significant increase in the probability or consequences of an accident previously evaluated, or 2) create the possibility of a new or different kind of accident from any accident previously evaluated, or 3) involve a significant reduction in a margin of safety.

Dominion has evaluated if a significant hazards consideration (SHC) is involved with the proposed change. A discussion of these standards as they relate to this change request is provided below.

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change relocates Technical Specification (TS) 4.2, "Augmented Inspections," TS 4.15, "Augmented Inservice Inspection Program for High Energy

Serial No.14-158 Docket Nos. 50-280/281 Attachment I Page 5 of 7 Lines Outside of Containment," and the associated TS Bases to the Surry Technical Requirements Manual (TRM). In addition, TS 6.4.U, "Augmented Inspections and Examinations," will be added to the Surry TS. The proposed relocation of the TS 4.2 and TS 4.15 requirements to the TRM is appropriate since these requirements do not satisfy the categories and criteria of 10CFR50.36(c), which specifies what items qualify for inclusion in the TS.

Specifically, the TS 4.2 augmented inspections of the low head safety injection piping located in the valve pit, the reactor coolant pump flywheel, the low pressure turbine rotor blades, sensitized stainless steel, and TS 4.15 augmented inspections of the welds in the main steam and main feedwater lines in the main steam valve house of each unit will be relocated to the TRM. The augmented inspections, which are performed in addition to required ASME Code Section Xl inspections/examinations, will continue to be performed as required by the TRM.

The plant systems and components to which the augmented inspections apply will not be operated in a different manner. The proposed relocation of the augmented inspections does not involve a physical change to the plant or a change in the manner in which the plant is operated or controlled.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed change does not involve any physical alteration of plant equipment.

As such, no new or different types of equipment will be installed, and the basic operation of installed plant systems and components, to which the augmented inspections apply, is unchanged.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The proposed change will not reduce a margin of safety because the relocation of the augmented inspections to the TRM has no impact on any safety analysis assumptions, as indicated by the fact that the requirements do not meet the

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 6 of 7 10CFR50.36(c) criteria for inclusion in the TS. In addition, the augmented inspections will be moved to the TRM without change and will continue to be performed as required by the TRM.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above, Dominion concludes that the proposed changes do not represent a significant hazards consideration under the standards set forth in 10CFR50.92(c).

5.0 ENVIRONMENTAL CONSIDERATION

This license amendment request meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9) as follows:

(i) The amendment involves no significant hazards consideration.

As described above, the proposed license amendment request does not involve a significant hazards consideration.

(ii) There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

The proposed license amendment request relocates the TS 4.2 and TS 4.15 augmented inspection requirements to the TRM and does not affect the types or amounts of effluents that may be released offsite. Therefore, there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.

(iii)There is no significant increase in individual or cumulative occupational radiation exposure.

The proposed license amendment request relocates the TS 4.2 and TS 4.15 augmented inspection requirements to the TRM and does not affect individual or cumulative occupational radiation exposure. Therefore, there is no significant increase in individual or cumulative occupational radiation exposure.

Based on the above assessment, Dominion concludes that the proposed change meets the criteria specified in 10CFR51.22 for a categorical exclusion from the requirements of 10CFR51.22 relative to requiring a specific environmental assessment or impact statement by the Commission.

Serial No.14-158 Docket Nos. 50-280/281 Attachment 1 Page 7 of 7

6.0 CONCLUSION

The proposed license amendment request relocates TS 4.2, "Augmented Inspections,"

TS 4.15, "Augmented Inservice Inspection Program for High Energy Lines Outside of Containment," and the associated TS Bases to the Surry TRM and adds TS 6.4.U, "Augmented Inspections and Examinations," to the Administrative Controls Section 6.4, "Unit Operating Procedures and Programs." The proposed change is appropriate because the TS 4.2 and TS 4.15 requirements do not satisfy the 10CFR50.36(c) categories and criteria for inclusion of information in the TS. The augmented inspections, which are performed in addition to required ASME Code Section XI inspections/examinations, will continue to be performed as required by the TRM.

7.0 REFERENCES

7.1 Atomic Safety and Licensing Board, In the Matter of Virginia Electric and Power Company (Surry Power Station, Unit 1), Docket No. 50-280, Initial Decision on Issue of Welds and Welding Practices,dated April 26, 1972.

7.2 Letter from R. C. DeYoung of the US Atomic Energy Commission to Mr. E. B.

Crutchfield of Virginia Electric and Power Company dated May 25, 1972, that issued Facility Operating License DPR-32 for Surry Power Station Unit 1 and associated Technical Specifications.

7.3 NRC letter dated September 21, 1973- Issuance of Section 4.15, Change No. 13 -

Augmented Inservice Inspection Program for High Energy Lines Outside of Containment 7.4 NRC letter dated May 24, 1989 -

Subject:

Surry Units 1 and 2 - Issuance of Amendments re: Inservice Inspection and Testing Requirements (TAC Nos. 56910 and 56911)

Serial No.14-158 Docket Nos. 50-280/281 Attachment 2 MARKED-UP TECHNICAL SPECIFICATIONS AND BASES PAGES Virginia Electric and Power Company (Dominion)

Surry Station Units 1 and 2

TS ii TECHNICAL SPECIFICATION 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 DELETED 3.20 SHOCK SUPPRESSORS (SNUBBERS) TS 3.20-1 3.21 MAIN CONTROL ROOM/EMERGENCY SWITCHGEAR ROOM TS 3.21-1 (MCRfESGR) EMERGENCY VENTILATION SYSTEM (EVS) 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS TS 3.22-1 3.23 MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM TS 3.23-1 AIR CONDITIONING SYSTEM 4.0 SURVEILLANCE REQUIREMENTS TS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW TS 4.1-1 4.2 AUGMENTED INSPECTIONS R-jocATt-:'

R 0 "M

-iZ TS 4.2-1 4.3 DELETED 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 RCS OPERATIONAL LEAKAGE TS 4.13-1 4.14 DELETED Amendment Nos. 26apA 266

TS iii TECHNICAL SPECIFICATION TABLE OF CONTENTS SECTION TITLE PAGE 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH TS 4.15-1 ENERGY LINES OUTSIDE OF CONTAINMENT ("a .c A-r L -m -neM) 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE TS 4.16-1 MATERIALS SOURCES 4.17 SHOCK SUPPRESSORS (SNUBBERS) TS 4.17-1 4.18 MAIN CONTROL ROOM/EMERGENCY SWITCHGEAR ROOM TS 4.18-1 (MCR/ESGR) EMERGENCY VENTILATION SYSTEM (EVS) TESTING 4.19 STEAM GENERATOR (SG) TUBE INTEGRITY TS 4.19-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM TS 4.20-1 5.0 DESIGN FEATURES TS 5.0-1 5.1 SITE LOCATION TS 5.0-1 5.2 REACTOR CORE TS 5.0-1 5.3 FUEL STORAGE TS 5.0-2 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 AND PROGRAMS 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. "6" .....

TS 4.2-1 4.2 AUGMENTED

... T 4. INSPECTIONS 2- 2""-"l , k 5 4/ av 6c-, -v-0LOc,-r1"

-' "TO dr y.

+ApP+cability " ///

_bvApplies t 'ervice inspections *ichi augment toe qu/ired by ASM ection XI.

To provide the a itional assurance n essary for the co inued integrity of i portant components volved in safety an ant operation.

A. Inspections sh be performed specified in TS. le 4.2-1. Nondest tive examinati techniques an cceptance criteria all be in complian with the requ* ments of ASME ction XI.

The normal ins tion interval is 10 ye s.

C. Detailed ecords of each ins ction shall be mai med to allow a c tinuing ev ation and compariso ith future inspection The inspection ogram for ASME Se on XI of the ASME oiler and Pressure V sel Code lim* its inspection to AS Code Class 1, 2, d 3 components and/<ports.

Cert components, under i cellaneous Inspecti in this section, were ded because no corresponding co requirement. This ded requirement pro *des the inspection necessary to insur e continued integnt f these components.

Iteml1.4 The w pressure turbine r r blades are normall inspected concurrent , the disk and ub inspections. The sk and hub inspectio requency is based o xisting crack size, crack growth rat , and system operatin onditions. ASME Se ion XI does not prov e specific ex ination requirement or acceptance criteri or turbine rotor ins ctions.

Proce s and acceptance c ra for turbine rotor in ections are consiste ith general i stry practices.

Z x Amendment Nos. *43-and242--

Sens .ized stai ess steel augme d inspections were dded to assure pipi gintegrity of t classifi tion.

Items 2 .1-2.1.3 Th examinations r uired by these it s utilize the perio ically updated ASME ection XI Boiler d Pressure Vessel de for the augmente examinations. surface and volumetric xaminations requir by items 2.1.1 and .1.2 will be con cted at three times the fre uency required by te Code in an interva In addition to t Code required pressure sting, visual exami tions will be conduct d, while the pipi g is pressurized by the pr edures defined in bles 4.1-3A & B of echnical Specifi ation 4.1, concerning flu ing of sensitized st lness steel piping. W d selection crit a are modified from th ode for Class 1 we s, since stress level ' formation as c elated to weld locatio is unavailable for Su y.

Item 2.2.1 The sensi zed stainless steel lo ted in the conta' ment and recirculation pray rings in the ov ead of containment e classified AS Class 2 components. T ese compone s are urrently exempted by ASME Section from surface and vol etric exami tion quirements. As such an augmented ogram will remain in ace requirin visual (VT-1) examination these compone s for evidence of cracki g. Additional , sections of the piping will e examined by liquid penetrant inspectio when the pip* g is visually inspected.

-Iemnendm.t NOS. 213 -nd 42

T'LE 4.2-1 CTION A. MISCELLANEO SPECTIONS Re ui Required Examinatio Examination 0-Year Ite 0. Area Methods Interva srection \ jRemarks 1.1 Deleted 1.2 Low Head SIS Visual Non-applicable This pipe shall be vistIly ing located nspected once per 18 mi ths.

in ye pit Primary mp See remarks e remarks Inspec: Qnce every 20 years by a Flywheel qualified l lace UT examination over the volure from the inner bore of the flywheel tQNthe circle of one-half the outer" adius or a surface examination (MT ank PT) of exposed surfaces definedbý the

\,volume of the disassembled wheels.

The"rovisions of Specification 4.

are not"ia picable.

1.4.ow Pressure Visu and See rem s 100% of blaidsevery six operating u ne Rotor Magne years. Inspectio'Ns are normally Particle or

- performed concurr t with LP turbine Dye Penetrant rotor disk and hub ins ons.

EI El ELE 4.2- 1(continued SECTION B. SENSITIZED AINLESS STEEL N Required equired Examination Exa *ation 10- r Ite No.hore IInterval Inspe'on Remarks 2.1.1 Class I As required by e welds examined by A minimum of 5% o e welds shall be N circumferentia, ASME vo etc or surface e med once per 18 mi s. At least longitudinal, ction XI techniqu shall be 75% he total population of, elds branch pipe conducted at ee times shall be ekxauined each interval.

c ection, and the frequency req d same welds m e selected in subse-by ASME Section XI quent intervals for mination. See Class 2 r1.2 required by The we examined by A minimnn of 2.5% of the we shall circumferential, AS volumetric od rface be examineZ ,ce per 18 months.

ngitudinal, Section techniques shall least 22.5% of tReA!otal population of bra ipe *conducted at three tim welds shall be examined each interval.

connecti and frequency required e same welds may be selec.ted in sub-socket welds by A Section XI sequ intervals for examinati. See N *...... * *Note 1.

• 2.1 .3'N-.,Class 1 and Visual ( as As required by AS In addition to the required exami-Cta$ 2 sensitized required by Section XI atons the affected pip' shall be visu-stainles teel ASME al VT-2) examined dunn e I pieces Section XI flushin Tables 4.1-uirements of T.S.

nd34.1-3B.

Q.

TABLE 4.2-1 ntinued)

SECT N B. SENSITIZED STA S STEEL Required Required amination E ination I1-Year Item No. rea Me rval Inspection marks 2.2.1 Containment Visual (VT-i) an (See rem s) At t 25% of the exa rations Recirculation surface examination shall ha been completed the Spray Piping expiration one-third of the inspection inte al and at least 50 hall have been coilleted by the tion of two-third of the inspe on interval. The rb aining required examina ns shall be comprep d by the end oftheinspec . n interval. Surfa examinations wi include 6 patches ch 9 inches squa evenly dist 'uted around each ray Note 1: a)The minations shall be distnb t d among the systems promd, to the degree practi ble, on the numb of senitie tils te ed in eac stem (i.e., if a system c ains 30% of the welds, en 30% of the re ired b) Within a system te al ends (e.g., branch con tions, pipe to pump, Pip p valve) shall be selec The remainder of the selection shall se structural discontinuitie ipe fittings) prorated to degree practicable t e mber of discontinuities in t system. Other selectio say be necessary e h otal weld selectio riteria.

c) Within ch system, examinations s 1 be distributed between "ne sizes prorated to the ree practicable.

TS 4.15-1 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT (IZ LOCA-r"T"e -ro -rR'"

Appl bil" p .s tolwe sinpi gsystemsor ions of system ocated outsi of containm t wher rotecti from t consequences postulated rupt s is not provd d by a syste of pipe hip re aints, t impingement arriers, protect* enclosures d/or other easures esigned 00 speci ally to cope wit uch ruptures.

or Surry Units nd 2, this speci ation applies t welds in the ain stea and main fee ater lines in the ain steam valve use of each u Obj ive o provide assu ce of the conti ued integrity f the pipi systems ove eir service lf ime.

Specifica ns .,

A. For the 20 ds identifie n TS Figur 4.15:

1. the first re ing outage eriod a volu ric examinatio shall be perfo ed with 100 perc inspection welds in acc ance with ther quirement of E Section XI de, Inservic, nspection of clear Power PI t Componentso 75 Ie44.

sz-sA.1 -/ amdI iwe Amendment Nos. .24.2..,d--2i

CHANGE .13 stablish syste integrity and basmine data. /erfo

.The inse ice inspection; aeach weld shall b performed in acc ance with th requ' ments of ASME ection XI Code, Ins vice Inspection of uclear Power P nt omponents, with e following schedu (The inspection i ervals identifie elow sequentially fol w the baseline exa nation of TS 4.15. .1 above):

Fi 10 Year Inspectig Program Intervals

a. F* t 3-1/3 years (or 100% volumet inspection of all Ids earest refueling outa/

Second 3-1/3 year or 100% vo metric inspection oall welds nearest refuelin utage)

c. Third 3-1//3 ears (or 10 o volumetric inspec on of all welds nearest re 6eling outage) // /

SECCeSsi InspectionIntervals . .

Eve 0 years thereafter (or Volumetric ins ction of 1/3 of e welds at the ne est refueling outage) expiration of ach 1/3 of the 'spection inter with a cumulativ 00% coverag f all welds Note - The welds se cted during each insp tion period sh be distributed mong the total num ds"r. to be examined to pr ide a represen tive. sampling the conditions of te /. .

3. Exami tions that reveal u cceptable st ctural defec in a weld du i g an ins ction under TS 4.15. .2 shall be ex. nded to requi an additional in ection of nother 1/3 of the wel . If further u acceptable de cts are detected the second sampling, the remai der of the we s shall be ins cted.

H,-,., 4. the event airs of any wel are req ed following ny examinaf n during successiv inspection interv s, the ins ction schedul or the repair welds will revet ack to the first 10 ear inspec on program.

B. For welds other than ose identi d in TS Figur .15:

1. Welds in the in steam ii es including th safety valve aders and in the fe dwater lines in t main ste valve house hall be exa ned in accordan with the requir ents of su ection IWC of e dn ASME Sec XI Code.

C. For a welds in th main steam va e house:

A visua nispection of t esurface of t insulation at al weld locations s all be perf med on a wee y basis for d ection of leaks. ny detected lea ,shall be estigated and ealuated. If the akage is caused a through-wall 4,w either t plant shall be utdown, or t leaking piping i olated. Repairs s 11 be perfo ed prior to re mn of this line service.

2. Repa' s, reexaminati and piping pre ure tests shall be onducted i accordance w, the rules of ME Section XI ode.

Ame~ndment NOS. .2142 2Qnd 11

HA/NGE .13

'Basis, nider norma ]ant operatin onditions, e piping mater' s operate under ctile conditi s and with' the stress limi considerab below the ulti ate strength prop ies of the m erials.

Flaw which could w under s conditions ar generally associ ed with cycli oads that fique the metal nd to lead leakage cracks he inservice ex ination and t efrequency of inspection wi provide a eans for timely etection even be re the flaw p etrates the wall of the pipi.

/Hhýt /T /1 e.t SEPT. 1, 1973

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We,

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Mons, am onawm:

MAIN EAN 4 FEEDWTIR LIMB DESIGNATES AWTIft O'DINTS OPERAYNG tc

/ LINE NUMB[ R J,(-V0pD.J09-&01 RUPTURE

/61 241.244AW4249 Ts TEMP PICESS

("r) (PSIG) 4W 103

$4 w-WIPP0.113-601 101 w 490 1 2 MAIN EAM AND FEEDW ER 450 032 W.WFIDD-117-601 SeG LINE -UNIT 2 30'6#0-103-601 ^ 976 A 277 947ý? Su Y POWER STATION 3W-S"P-102- 135,1345 A 136 1005 47 1005 ITS I AND 2 (A 10-SMP-124-601 C)

/

A~m~ndrncnt N~,. 212 and 212

", y, gpc*..cp4edc Qrv,, &/.J S5r,,I &k.'.-Z-.11 TS6.4-15 spl 6,3ý- Ap7(wqv rn3 es-tec 61 4/,4o/2ot-i

4. Measurement, at designated locations, of the MCR/ESGR envelope pressure relative to all external areas adjacent to the MCR/ESGR envelope boundary during the pressurization mode of operation by one train of the MCR/ESGR EVS, operating at the flow rate required by TS 4.20, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the MCR/ESGR envelope boundary.

5. The quantitative limits on unfiltered air inleakage into the MCRIESGR envelope.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph 3. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of MCR/ESGR envelope occupants to these hazards will be within the assumptions in the licensing basis.

6. The provisions of SR 4.0.2 are applicable to the Frequencies for assessing MCR/ESGR envelope habitability, determining MCR/ESGR envelope unfiltered inleakage, and measuring. MCR/ESGR envelope pressure and assessing the MCR/ESGR envelope boundary as required by paragraphs 3 and 4, respectively.

S. Surveillance Frequency Control Program (SFCP)

This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specification are performed at interval sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

T. Inservice Examination. Testing. and Service Life Monitoring Program for Snubbers This program conforms to the examination, testing, and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (ISI) requirements for supports. The program shall be in accordance with the following:

Amendment Nos.

" *T S 7 a r . s .eJr-* qc d - w

- cq'r LC4 "* ",jl . I * "?-.. TS 6 .4-16 cnIs os - Aee,,v.ad "/l o.tC

a. This program shall meet 10 CFR 50.55a(g) requirements for supports.

b. The program shall meet the requirements of ISI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV)

Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b),

subject to its limitations and modifications, and subject to Commission approval.

c. The program shall, as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," in lieu of Section XI of the ASME BPV Code ISI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications listed therein.

Amendment Nos.

INSERT ON PAGE TS 6.4-16:

U. Augmented Inspections and Examinations The following augmented inspections and examinations have been relocated from the Technical Specifications to the Technical Requirements Manual (TRM):

1. Augmented Inspections - Inservice inspections augmenting those required by ASME Section Xl shall be performed to provide the additional assurance necessary for continued integrity of important components involved in safety and plant operation (e.g., the low head safety injection piping in the valve pit, the reactor coolant pump flywheel, the low pressure turbine blades, and sensitized stainless steel).

2. Augmented Inservice Inspection of High Energy Lines Outside of Containment -

In accordance with the Augmented Inservice Inspection Program for High Energy Lines Outside of Containment, examinations of welds in the main steam and main feedwater lines in the main steam valve house of each unit shall be performed to provide assurance of the continued integrity of the piping systems over their service lifetime. These requirements apply to welds in piping systems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed specifically to cope with such ruptures.

Serial No.14-158 Docket Nos. 50-280/281 Attachment 3 PROPOSED TECHNICAL SPECIFICATIONS AND BASES PAGES Virginia Electric and Power Company (Dominion)

Surry Station Units 1 and 2

TS ii TECHNICAL SPECIFICATION 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 DELETED 3.20 SHOCK SUPPRESSORS (SNUBBERS) TS 3.20-1 3.21 MAIN CONTROL ROOM/EMERGENCY SWITCHGEAR ROOM TS 3.21-1 (MCR/ESGR) EMERGENCY VENTILATION SYSTEM (EVS) 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS TS 3.22-1 3.23 MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM TS 3.23-1 AIR CONDITIONING SYSTEM 4.0 SURVEILLANCE REQUIREMENTS TS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW TS 4.1-1 4.2 AUGMENTED INSPECTIONS (RELOCATED TO TRM) TS 4.2-1 4.3 DELETED 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 RCS OPERATIONAL LEAKAGE TS 4.13-1 4.14 DELETED Amendment Nos.

TS iii TECHNICAL SPECIFICATION TABLE OF CONTENTS SECTION TITLE PAGE 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH TS 4.15-1 ENERGY LINES OUTSIDE OF CONTAINMENT (RELOCATED TO TRM) 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE TS 4.16-1 MATERIALS SOURCES 4.17 SHOCK SUPPRESSORS (SNUBBERS) TS 4.17-1 4.18 MAIN CONTROL ROOM/EMERGENCY SWITCHGEAR ROOM TS 4.18-1 (MCR/ESGR) EMERGENCY VENTILATION SYSTEM (EVS) TESTING 4.19 STEAM GENERATOR (SG) TUBE INTEGRITY TS 4.19-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM TS 4.20-1 5.0 DESIGN FEATURES TS 5.0-1 5.1 SITE LOCATION TS 5.0-1 5.2 REACTOR CORE TS 5.0-1 5.3 FUEL STORAGE TS 5.0-2 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 AND PROGRAMS 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.

TS 4.2-1 4.2 AUGMENTED INSPECTIONS (RELOCATED TO TRM) I Pages TS 4.2-2 through TS 4.2-5 have been deleted.

I Amendment Nos.

TS 4.15-1 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT (RELOCATED TO TRM)

Pages TS 4.15-2 through TS 4.15-4 and TS Figure 4.15 have been deleted. I Amendment Nos.

This page excerpted from letter Serial No.13-271 (5/13/2013) - TS 6.4-15 Approval requested by 4/30/2014.

4. Measurement, at designated locations, of the MCR/ESGR envelope pressure relative to all external areas adjacent to the MCR/ESGR envelope boundary during the pressurization mode of operation by one train of the MCR/ESGR EVS, operating at the flow rate required by TS 4.20, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the MCR/ESGR envelope boundary.

5. The quantitative limits on unfiltered air inleakage into the MCR/ESGR envelope.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph 3. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of MCR/ESGR envelope occupants to these hazards will be within the assumptions in the licensing basis.

6. The provisions of SR 4.0.2 are applicable to the Frequencies for assessing MCR/ESGR envelope habitability, determining MCR/ESGR envelope unfiltered inleakage, and measuring MCR/ESGR envelope pressure and assessing the MCR/ESGR envelope boundary as required by paragraphs 3 and 4, respectively.

S. Surveillance Frequency Control Program (SFCP)

This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specification are performed at interval sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

T. Inservice Examination, Testing, and Service Life Monitoring Program for Snubbers This program conforms to the examination, testing, and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (ISI) requirements for supports. The program shall be in accordance with the following:

Amendment Nos.

This page excerpted from letter Serial No.13-271 TS 6.4-16 (5/13/2013) - Approval requested by 4/30/2014

a. This program shall meet 10 CFR 50.55a(g) requirements for supports.

b. The program shall meet the requirements of ISI of supports set forth in subsequent edition of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b), subject to its limitations and modifications, and subject to Commission approval.

c. The program shall, as allowed by 10 CFR 50.55a(b)(3)(V), meet Subsection ISTA, "General Requirements," and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," in lieu of Section XI of the ASME BPV Code 1SI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(V)) subject to the limitations and modifications listed therein.

U. Augmented Inspections and Examinations The following augmented inspections and examinations have been relocated from the Technical Specifications to the Technical Requirements Manual (TRM):

a. Augmented Inspections - Inservice inspections augmenting those required by ASME Section XI shall be performed to provide the additional assurance necessary for continued integrity of important components involved in safety and plant operation (e.g., the low head safety injection piping in the valve pit, the reactor coolant pump flywheel, the low pressure turbine blades, and sensitized stainless steel).

b. Augmented Inservice Inspection of High Energy Lines Outside of Containment

- In accordance with the Augmented Inservice Inspection Program for High Energy Lines Outside of Containment, examinations of welds in the main steam and main feedwater lines in the main steam valve house of each unit shall be performed to provide assurance of the continued integrity of the piping systems over their service lifetime. These requirements apply to welds in piping systems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed specifically to cope with such ruptures.

Amendment Nos.