NL-21-0989, License Amendment Request to Relocate Augmented Piping Inspection Program Details

License Amendment Request to Relocate Augmented Piping Inspection Program Details

ML21356B484
Person / Time
Site:	Vogtle, Farley
Issue date:	12/22/2021
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-21-0989
Download: ML21356B484 (21)

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Southern Nuclear Operating Company Joseph M. Farley Nuclear Power Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2

License Amendment Request to Relocate Augmented Pip ing Inspection Program Details from Technical Specifications to a Licensee Control led Document

Enclosure

Evaluation of Proposed Change

Evaluation of Proposed Change

1.0

SUMMARY

DESCRIPTION

Southern Nuclear Operating Company (SNC) hereby req uests a license amendment to Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2 renewe d facility operating licenses NPF-2 and NPF-8, respectively, and Vogtle Electric Generating Plant (VEGP) Units 1 and 2 renewed facility operating licenses NPF-68 and NPF-81, respectively.

The proposed change will revise the FNP Technical S pecifications (TS) by relocating some detailed information from TS 5.5.16, Main Steamlin e Inspection Program, to the FNP Updated Final Safety Analysis Report (UFSAR). The proposed change also revises the VEGP TS by relocating some detailed information from TS 5.5.16, MS and FW Piping Inspection Program, to the VEGP UFSAR. A program description will remai n in TS 5.5.16 for each plant. The UFSARs for each plant will be updated in accordance with 10 CFR 50.71(e).

The proposed changes are requested to remove detail from the TS and to provide a consistent program description for this augmented inspection p rogram. To determine if information in these TS can be relocated to licensee control, these chan ges are compared to the criteria in 10 CFR 50.36(c) with regard to what items are contained in TS.

2.0 DETAILED DESCRIPTION

2.1 Regulatory Basis

TS 5.5.16 for each plant provides details of an aug mented inservice inspection program for high energy lines outside of containment. These requirem ents apply to welds in piping systems or portions of piping systems located outside of conta inment 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 thei r service life. These requirements are contained in the UFSARs for both FNP and VEGP. The requirements were addressed during initial licensing of both plants as described below.

Farley The main steam line break for FNP is not postulated for main steam piping outside containment up to and including the main steam isolation valves. The basis for this position is discussed in UFSAR Appendix 3K, which describes the criteria for postulating pipe ruptures or cracks in high-energy lines outside containment and the methods fo r evaluating the effects of these breaks.

Attachment A, Part II, of Appendix 3K specifically addresses the postulated break and leakage locations in the main steam lines outside of contai nment and demonstrates that this piping conforms to Branch Technical Positions (BTP) APCSB 3-1 and MEB 3-1 of Standard Review Plan (SRP) Sections 3.6.1 and 3.6.2, respectively. This is consistent with Section 3.6 of Supplement 1 of the NRC Safety Evaluation Report fo r the Joseph M. Farley Nuclear Plant -

Units 1 and 2 (Reference 1).

As described in UFSAR Appendix 3K, Part II, Section D, inservice examination and related design provisions in the containment penetration ar ea and throughout the no break region should address location of protective measures and scope of the augmented inspection. The protective measures, structures, and guard pipes sh ould not prevent the access required to conduct the inservice examinations specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Division 1, Rules for Inspection and

E-1 T e s t in g o f C o m p o n e n t s in L ig h t - W a t e r C o o le d P la n t s. F o r t h o s e p o r t io n s o f f lu id s y s t e m p ip in g id e n t if ie d in B. 2. c o f A P C S B 3 - 1, t h e e x t e n t o f in s e r v ic e e x a m in a t io n s c o m p le t e d d u r in g e a c h in s p e c t io n in t e r v a l s h o u ld p r o v id e 1 0 0 - p e r c e n t v o lu m e t r ic e x a m in a t io n o f c ir c u m f e r e n t ia l a n d lo n g it u d in a l p ip e w e ld s w it h in t h e b o u n d a r y o f t h e s e p o r t io n s o f p ip in g t o th e e x t e n t p r a c t ic a l.

V o g t le A s d e s c r ib e d in t h e V o g t le U F S A R, S e c t io n 3. 6. 1, t h e s e le c t io n o f p ip e f a ilu r e lo c a t io n s a n d e v a lu a t io n o f t h e c o n s e q u e n c e s o n n e a r b y e s s e n t ia l s y s t e m s, c o m p o n e n ts, a n d s tr u c t u r e s a r e in a c c o r d a n c e w it h t h e r e q u ir e m e n ts o f 1 0 C F R 5 0, A p p e n d ix A, G e n e r a l D e s ig n C r it e r io n, a n d B T P s A S B 3 - 1 a n d M E B 3 - 1.

T h e N u c le a r R e g u la t o r y C o m m is s io n ( N R C ) r e v ie w e d a n d a d d r e s s e d t h e s e le c t io n o f p ip e f a ilu r e lo c a t io n s in t h e N R C S a f e t y E v a lu a t io n R e p o r t f o r V o g t le ( R e f e r e n c e 2 ). S e c t io n 3 d e s c r ib e s t h a t t h e m a in s t e a m a n d f e e d w a t e r s y s te m s u p t o t h e f ir s t r e s tr a in t o u t s id e c o n t a in m e n t a r e c la s s if ie d a s p a r t o f t h e b r e a k e x c lu s io n b ou n d a r y a s d e f in e d in it e m B. 1. 6 o f B T P M E B 3 - 1, P o s t u la te d B r e a k s a n d L e a k a g e L o c a t ion s in F lu id S y s t e m P ip in g O u t s id e C o n t a in m e n t. F o r h ig h e n e r g y p ip in g w it h in t h e c o n t a in m e n t p e n e t r a t io n a r e a w h e r e b r e a k s are n o t p o s t u la t e d, S R P S e c t io n 3. 6. 2 s e t s f o r t h c e r t a in c r it e r ia f o r t h e a n a ly s is a n d s u b s e q u e n t a u g m e n t e d in s e r v ic e in s p e c t io n r e q u ir e m e n t s. B r e a k s n e e d n o t b e p o s t u la t e d in t h o s e p o r t io n s o f p ip in g w it h in t h e c o n t a in m e n t p e n e t r a t io n r e g io n t h a t m e e t t h e r e q u ir e m e n t s o f A S M E C o d e S e c t io n II I, S u b a r t ic le N E - 1 1 2 0 a n d t h e a d d it io n a l r e q u ir e m e n t s o u t lin e d in B T P M E B 3 - 1 o f S R P S e c t io n 3. 6. 2. A u g m e n t e d in s e r v ic e in s p e c tio n is r e q u ir e d f o r t h o s e p o r t io n s o f p ip in g w it h in t h e b r e a k e x c lu s io n r e g io n.

U F S A R S e c t io n 6. 6. 8 d e s c r ib e s t h e a u g m e n te d in s e r v ic e in s p e c t io n p r o g r a m f o r h ig h - e n e r g y f lu id s y s t e m s p ip in g b e t w e e n c o n t a in m e n t is o la t io n v a lv e s o r w h e r e n o is o la t io n v a lv e is u s e d in s id e c o n t a in m e n t, b e t w e e n t h e f ir s t r ig id p ip e c o n n e c t io n t o t h e c o n t a in m e n t p e n e t r a t io n o r t h e f ir s t p ip e w h ip r e s tr a in t in s id e c o n t a in m e n t a n d t h e o u t s id e is o la t io n v a lv e. T h is p r o g r a m in c lu d e s 1 0 0 p e r c e n t v o lu m e tr ic e x a m in a t io n o f c ir c u m f e r e n t ia l a n d lo n g it u d in a l p ip e w e ld s in t h e a f f e c t e d p ip in g d u r in g e a c h in s p e c t io n in t e r v a l a n d is c o n d u c t e d in a c c o r d a n c e w it h A S M E C o d e, S e c t io n X I, a n d c o v e r s t h e h ig h - e n e r g y f lu id s y s t e m s d e s c r ib e d in U F S A R s u b s e c t io n s 3. 6. 1 a n d 3. 6. 2.

F N P U n it s 1 a n d 2 5. 5. 1 6 M a in S t e a m lin e I n s p e c t io n P r o g r a m

T h e t h r e e m a in s t e a m lin e s fr o m t h e r ig id a n c h o r p o in t s o f t h e c o n t a in m e n t p e n e t r a t io n s d o w n s t r e a m t o a n d in c lu d in g t h e m a in s t e a m h e a d e r s h a ll b e in s p e c t e d. T h e e x t e n t o f t h e in s e r v ic e e x a m in a t io n s c o m p le t e d d u r in g e a c h in s p e c t io n in t e r v a l ( IW A 2 4 0 0, A S M E C o d e,

1 9 7 4 E d it io n, S e c t io n X I) s h a ll p r o v id e 1 0 0 p e r c e n t v o lu m e tr ic e x a m in a t io n o f c ir c u m f e r e n t ia l a n d lo n g itu d in a l p ip e w e ld s t o t h e e x t e n t p r a c t ic a l. T h e a r e a s s u b je c t t o e x a m in a t io n a r e t h o s e d e f in e d in a c c o r d a n c e w it h e x a m in a t io n c a t e g o r y C - G f o r C la s s 2 p ip in g w e ld s in T a b le I W C - 2 5 2 0.

2.2 C u r r e n t T e c h n ic a l S p e c if ic a t io n R e q u ir e m e n t s

C u r r e n t T S 5.5.1 6

E valu atio n o f P ro p o sed C h an g e

E -2

Evaluation of Proposed Change

VEGP Units 1 and 2 5.5.16 MS and FW Piping Inspection Program

This program shall provide for the inspection of th e four Main Steam and Feedwater lines from the containment penetration flued head outboar d welds, up to the first five-way restraint. The extent of the inservice examinations completed during each inspection interval (ASME Code Section XI) shall provide 100% volumetric examination of circumferential and longitudinal welds to the exten t practical. This augmented inservice inspection is consistent with the requirements of N RC Branch Technical Position MEB 3-1, "Postulated Break and Leakage Locations in Fluid Sy stem Piping Outside Containment,"

November 1975 and Section 6.6 of the FSAR.

2.3 Reason for the Proposed Change

The proposed changes are requested to relocate deta il from the TS to the plants UFSARs and to provide a consistent program description for thi s augmented inspection program. The TS details proposed for relocation from the TS are des criptions of inspections to be performed on plant equipment. These details are design basis inf ormation and are more appropriately contained in the respective plants UFSARs. Therefo re, SNC requests relocation of these TS details to the respective plants UFSARs as describ ed below.

2.4 Description of the Proposed Change

Proposed TS Change

FNP Units 1 and 2 5.5.16 Main Steamline Inspection Program

In accordance with the augmented inservice inspecti on program for high energy lines outside of containment, examinations of welds in th e main steam lines of each unit shall be performed to provide assurance of the continued int egrity 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 protec tion from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measur es designed specifically to cope with such ruptures.

VEGP Units 1 and 2 5.5.16 MS and FW Piping Inspection Program

In accordance with the augmented inservice inspecti on program for high energy lines outside of containment, examinations of welds in th e main steam and main feedwater lines of each unit shall be performed to provide assuranc e of the continued integrity of the piping systems over their service lifetime. These requirem ents 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.

The current detailed program description contained in TS 5.5.16 will be relocated to the UFSARs for FNP and VEGP. The requirements in the c urrent TS 5.5.16 for each plant are

E-3 Evaluation of Proposed Change

already contained in each plants respective UFSAR. However, the specific verbiage of TS 5.5.16 will be included in each plants UFSAR as a concise description of the augmented inspection program. Specifically, the entire verbia ge of the FNP TS 5.5.16 will be relocated to the FNP UFSAR, Section 3K, Part II, Item D. Likewis e, the entire verbiage of the VEGP TS 5.5.16 will be relocated to the VEGP UFSAR, Section 6.6.8. Any UFSAR information that duplicates the relocated TS information may be edit ed for clarity. The UFSARs for each plant will be updated in accordance with 10 CFR 50.71(e).

No changes are proposed for any Limiting Condition for Operation in Section 3.0 of the FNP or VEGP TS in this request. Therefore, this license a mendment request is not linked to the previously submitted VEGP license amendment request to remove one Main Steam Isolation Valve System from TS 3.7.2 (ML21274A073).

3.0 TECHNICAL EVALUATION

Detailed discussion associated with FNP TS 5.5.16, Main Steamline Inspection Program, and VEGP TS 5.5.16, MS and FW Piping Inspection Progra m, are proposed to be relocated to the licensee controlled UFSARs as described above. Thes e detailed descriptions are replaced with program descriptions in TS 5.5.16 for each plant. T he program description is contained in each plants UFSAR. The licensing basis for the augment ed inservice inspection program of high energy piping outside of containment is not changed by the relocation of details about the inspection program from the TS to the UFSAR.

The FNP and VEGP requirements for the augmented ins pection program for high energy lines from the containment wall to and including the inbo ard or outboard isolation valves (per MEB 3-1, ASP 3-1 and APCSB 3-1) are consistent with the r equirements of BTP 3-4. BTP 3-4 is used below for easier reference.

10 CFR 50.36 Criteria

The augmented inspection program described in TS 5. 5.16 is one of several design criteria provided by the NRC in BTP 3-4 to establish a pipe break exclusion zone for ASME Class 2 secondary system high energy piping. This inspecti on is in addition to the inservice inspections of piping required by 10 CFR 50.55a. The augmented inspection is only applied to the secondary system piping for which plant designers d id not provide barriers, pipe whip restraints, or enclosures to protect against the effects of a p ostulated secondary system pipe rupture.

These sections of piping are described in each plan ts UFSAR.

The NRC has provided guidance for the contents of T S in 10 CFR 50.36(c). As a result, TS requirements which fall within or satisfy any of th e criteria in the regulation must be retained in the TS, while those requirements which do not fall within or satisfy these criteria may be relocated to licensee-controlled documents.

The regulatory requirements are listed below.

(1) Safety limits for nuclear reactors are limits u pon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity.

E-4 T h e d e ta ils in T S 5.5.1 6 w h ic h a r e b e in g r e lo c a te d to th e fa c ility U F S A R s a r e n o t s a fe ty lim its o r lim itin g s a fe ty s y s te m s e ttin g s. T h e y d e s c r ib e a n a u g m e n te d in s p e c tio n p r o g r a m fo r c e r ta in s e c o n d a r y s y s te m h ig h e n e r g y p ip in g. T h is p r o p o s e d T S c h a n g e d o e s n o t m e e t th e S a fe ty L im its c r ite r io n.

( 2 ) L im itin g c o n d itio n s fo r o pe r a tio n a r e th e lo w e s t fu n c tio n a l c a pa b ility o r pe r fo r m a n c e le v e ls o f e q u ipm e n t r e q u ir e d fo r s a fe o pe r a tio n o f th e fa c ility.

C r ite r io n 1 - In s ta lle d in s tr u m e n ta tio n th a t is u s e d to d e te c t, a n d in d ic a te in th e c o n tr o l r o o m, a s ig n ific a n t a b n o r m a l d e g r a d a tio n o f th e r e a c to r c o o la n t pr e s s u r e b o u n d a r y.

T h e d e ta ils in T S 5.5.1 6, w h ic h a r e b e in g r e lo c a te d to th e fa c ility U F S A R s, a r e n o t a p p lic a b le to in s ta lle d in s tr u m e n ta tio n w h ic h is u s e d to d e te c t, a n d in d ic a te in th e c o n tr o l r o o m, a n a b n o r m a l d e g r a d a tio n o f th e r e a c to r c o o la n t p r e s s u r e b o u n d a r y. It d e s c r ib e s a n a u g m e n te d in s p e c tio n p r o g r a m fo r c e r ta in s e c o n d a r y s y s te m h ig h e n e r g y p ip in g. T S 5.5.1 6 d o e s n o t a d d r e s s in s tr u m e n ta tio n a n d d o e s n o t im p a c t th e r e a c to r c o o la n t b o u n d a r y. N o p h y s ic a l c h a n g e to th e p la n t o r th e p ip in g in s p e c tio n p r o g r a m is p r o p o s e d b y th is r e q u e s t. T h is T S d o e s n o t m e e t C r ite r io n 1.

C r ite r io n 2 - A p r o c e s s v a r ia b le, d e s ig n fe a tu r e, o r o pe r a tin g r e s tr ic tio n th a t is a n in itia l c o n d itio n o f a d e s ig n b a s is a c c id e n t o r tr a n s ie n t a n a ly s is th a t e ith e r a s s u m e s th e fa ilu r e o f o r p r e s e n ts a c h a lle n g e to th e in te g r ity o f a fis s io n p r o d u c t b a r r ie r.

T h e d e ta ils o f T S 5.5.1 6, w h ic h a r e b e in g r e lo c a te d to th e fa c ility U F S A R s, a r e n o t a p p lic a b le to a p r o c e s s v a r ia b le, d e s ig n fe a tu r e, o r o p e r a tin g r e s tr ic tio n th a t is a n in itia l c o n d itio n o f a d e s ig n b a s is a c c id e n t o r tr a n s ie n t a n a ly s is th a t e ith e r a s s u m e s th e fa ilu r e o f o r p r e s e n ts a c h a lle n g e to th e in te g r ity o f a fis s io n p r o d u c t b a r r ie r. T h e d e ta ils d e s c r ib e a n a u g m e n te d in s p e c tio n p r o g r a m fo r c e r ta in s e c o n d a r y s y s te m h ig h e n e r g y p ip in g. N o p h y s ic a l c h a n g e to th e p la n t o r th e p ip in g in s p e c tio n p r o g r a m is p r o p o s e d b y th is r e q u e s t. T h e r e fo r e, th is T S d o e s n o t m e e t C r ite r io n 2.

C r ite r io n 3 - A s tr u c tu r e, s y s te m o r c o m po n e n t th a t is pa r t o f th e p r im a r y s u c c e s s pa th a n d w h ic h fu n c tio n s o r a c tu a te s to m itig a te a d e s ig n b a s is a c c id e n t o r tr a n s ie n t th a t e ith e r a s s u m e s th e fa ilu r e o f o r p r e s e n ts a c h a lle n g e to th e in te g r ity o f a fis s io n pr o d u c t b a r r ie r.

P e r B T P 3 - 4, th e a u g m e n te d in s p e c tio n p r o g r a m d e s c r ib e d in T S 5.5.1 6 is p a r t o f th e d e s ig n c r ite r ia u s e d to d e te r m in e th e p o s tu la te d b r e a k lo c a tio n s in c e r ta in s e c o n d a r y s y s te m h ig h e n e r g y lin e s in th e p o w e r p la n t. T h e T S d e s c r ib e s a p ip in g in s p e c tio n p r o g r a m. It d o e s n o t d e s c r ib e a s tr u c tu r e, s y s te m, o r c o m p o n e n t w h ic h fu n c tio n s o r a c tu a te s to m itig a te a d e s ig n b a s is a c c id e n t o r tr a n s ie n t th a t e ith e r a s s u m e s th e fa ilu r e o f o r p r e s e n ts a c h a lle n g e to th e in te g r ity o f a fis s io n p r o d u c t b a r r ie r. N o p h y s ic a l c h a n g e to th e p la n t o r th e p ip in g in s p e c tio n p r o g r a m is p r o p o s e d b y th is r e q u e s t. T h e r e fo r e, th is T S d o e s n o t s a tis fy c r ite r io n 3.

C r ite r io n 4 - A s tr u c tu r e, s y s te m o r c o m po n e n t w h ich o pe r a tin g e x pe r ie n c e o r pr o b a b ilis tic r is k a s s e s s m e n t h a s s h o w n to b e s ig n ific a n t to pu b lic h e a lth a n d s a fe ty.

N o s p e c ific T S - r e la te d s tr u c tu r e, s y s te m o r c o m p o n e n t is b e in g r e v is e d o r r e m o v e d fr o m th e T S.

P e r B T P 3 - 4, th e a u g m e n te d in s p e c tio n p r o g r a m d e s c r ib e d in T S 5.5.1 6 is p a r t o f th e c r ite r ia u s e d to d e te r m in e if p ip e b r e a k s m u s t b e p o s tu la te d in c e r ta in s e c o n d a r y s y s te m h ig h e n e r g y lin e s in th e p o w e r p la n t. T h is d e s ig n c r ite r ia, in c lu d in g th e a u g m e n te d in s p e c tio n p r o g r a m,

E valu atio n o f P ro p o sed C h an g e

E -5

e s t a b lis h e s t h a t c e r t a in s e c o n d a r y s y s t e m p ip e b r e ak s n e e d n o t b e a s s u m e d, a n d d e s ig n p r o v is io n s a r e n o t n e e d e d t o m it ig a t e t h e m. T h e r ef o r e, t h is T S d o e s n o t m e e t C r it e r io n 4.

( 3 ) S u r v e illa n c e r e q u ir e m e n t s. S u r v e illa n c e r e q u ir e m e n t s a r e r e q u ir e m e n t s r e la t in g t o t e s t, c a lib r a t io n, o r in spe c t io n t o a s s u r e t h a t t h e n e c e s s a r y q u a lit y o f s y s t e m s a n d c o m po n e n t s is m a in t a in e d, t h a t f a c ilit y o pe r a t io n w ill b e w it h in s a fe t y lim it s, a n d t h a t t h e lim it in g c o n d it io n s f o r o pe r a t io n w ill b e m e t.

T h e in s p e c t io n s d e s c r ib e d in T S 5. 5. 1 6 d o n o t m e e t t h e r e q u ir e m e n t s f o r a S R b e c a u s e t h e y a r e n o t r e la t e d t o t h e t e s t, c a lib r a t io n o r in s p e c t io n t o a s s u r e t h e n e c e s s a r y q u a lit y o f s y s t e m s a n d c o m p o n e n ts. T h e in s e r v ic e in s p e c t io n s n e e d e d t o a s s u r e t h e n e c e s s a r y q u a lit y o f s y s t e m s a n d c o m p o n e n ts a r e r e q u ir e d b y 1 0 C F R 5 0. 5 5 a. T h e a u g m e n t e d in s p e c t io n s a r e p e r f o r m e d in a d d it io n t o t h e A S M E C o d e S e c t io n X I in s p e c t io n s / e x a m in a t io n s r e q u ir e d b y 1 0 C F R 5 0. 5 5 a.

B o t h t h e r e q u ir e d in s e r v ic e in s p e c t io n a n d t h e a u g m e n t e d in s e r v ic e in s p e c t io n w ill c o n t in u e t o b e p e r f o r m e d in a c c o r d a n c e w it h t h e r e q u ir e m e n ts in e a c h p la n t s U F S A R. A d d it io n a lly, t h e N R C P o lic y S t a t e m e n t o n T e c h n ic a l S p e c if ic a t io n s ( R e f e r e n c e 3 ) in d ic a t e s t h a t S R s a r e a s s o c ia t e d w it h L im it in g C o n d it io n s f o r O p e r a t io n. T h e r e is n o L im it in g C o n d it io n f o r O p e r a t io n r e la t e d t o t h is p r o p o s e d c h a n g e. T h e r e f o r e, t h e s e d e t a ils d o n o t q u a lif y a s a S R in t h e T S.

( 4 ) D e s ig n f e a t u r e s. D e s ig n f e a t u r e s t o b e in c lu d e d a r e t h o s e f e a t u r e s o f t h e f a c ilit y s u c h a s m a t e r ia ls o f c o n s t r u c t io n a n d g e o m e t r ic a r r a n g e m e n t s, w h ic h, if a lt e r e d o r m o d if ie d, w o u ld h a v e a s ig n if ic a n t e f fe c t o n s a fe t y a n d a r e n o t c o v e r e d in c a t e g o r ie s d e s c r ib e d in pa r a g r a ph s ( c) ( 1 ),

( 2 ), a n d ( 3 ) o f t h is s e c t io n.

T h e in f o r m a t io n in T S 5.5. 1 6 a u g m e n t e d in s e r v ic e in s p e c t io n p r o g r a m f o r h ig h e n e r g y lin e s o u t s id e o f c o n t a in m e n t d o e s n o t d e s c r ib e a f a c ility d e s ig n f e a t u r e, s u c h a s m a t e r ia ls o f c o n s t r u c t io n a n d g e o m e tr ic a r r a n g e m e n t s, t h a t c o u ld h a v e a s ig n if ic a n t e f fe c t o n s a f e t y.

( 5 ) A d m in is t r a t iv e c o n tr o ls. A d m in is t r a t iv e c o n t r o ls a r e t h e pr o v is io n s r e la t in g t o o r g a n iz a t io n a n d m a n a g e m e n t, pr o c e d u r e s, r e c o r d k e e pi n g, r e v ie w a n d a u d it, a n d r e po r t in g n e c e s s a r y t o a s s u r e o pe r a t io n o f t h e fa c ilit y in a s a f e m a n n e r. E a c h lic e n s e e s h a ll s u b m it a n y r e po r t s t o t h e C o m m is s io n pu r s u a n tt o a p pr o v e d t e c h n ic a l spe c if ic at io n s a s spe c if ie d in § 5 0. 4.

T S 5. 5. 1 6 is n o t a n a d m in is t r a t iv e c o n tr o l r e la t in g t o o r g a n iz a t io n a n d m a n a g e m e n t, p r o c e d u r e s,

r e c o r d k e e p in g, r e v ie w a n d a u d it, a n d r e p o r t in g n e c e s s a r y t o a s s u r e s a f e o p e r a t io n. H o w e v e r, it is r e t a in e d in t h e A d m in is t r a t iv e C o n tr o ls s e c t io n. T h e p r o g r a m d e t a ils a r e r e lo c a t e d t o e a c h p la n t s U F S A R.

( 6 ) D e c o m m is s io n in g a p pl ie s o n ly t o n u c le a r po w e r pl a n t s t h a t h a v e s u b m it t e d d e c o m m is s io n in g c e r t if ic a t io n s

5 0. 7 3 w h e n r e q u ir e d.

T h e s e c r it e r ia d o n o t a p p ly t o t h e r e lo c a t io n o f in f o r m a t io n fr o m t h e T S t o t h e U F S A R.

A s d is c u s s e d a b o v e, t h e d e t a ils c o n t a in e d in T S 5. 5. 1 6 d o n o t s a t is f y t h e 1 0 C F R 5 0. 3 6 ( c )

c a t e g o r ie s a n d c r it e r ia f o r in c lu s io n o f in f o r m a t io n in T S. T h u s, r e lo c a t io n o f t h e d e t a ile d in f o r m a t io n f r o m T S 5. 5.1 6 t o t h e U F S A R o f e a c h p la n t is a p p r o p r ia t e.

( 8 ) W r it t e n R e po r t s. L ic e n s e e s m u s t s u b m it L ic e n s e e E v e n t R e po r t s in a c c o r d a n c e w it h 1 0 C F R

( 7 ) In itia l n o tific a tio n s a r e m a d e to th e N R C O pe r a tio n s C e n te r

E valu atio n o f P ro p o sed C h an g e

E -6

E valu atio n o f P ro p o sed C h an g e

4.0 R E G U L A T O R Y E V A L U A T IO N

4.1 A p p licab le R eg u lato ry R eq u irem en ts/C riteria

T he follow ing N R C requirem ents and guidance docum ents are applicable to the review of the proposed changes.

10 C F R 50.36(c) provides the requirem ents for item s that m ust be contained in plant T echnical S pecifications. A s described above the details associated w ith the augm ented inspection program for high energy piping outside containm ent do not m eet the criteria set forth in 10 C F R 50.36.

10 C F R 50.55a(g)(6)(ii) states that, "T he C om m ission m ay require the licensee to follow an augm ented inservice inspection program for system s and com ponents for w hich the C om m ission deem s that added assurance of structural reliability is necessary." T he augm ented inspections are perform ed in addition to required A S M E C ode S ection X I inspections or exam inations and w ill continue to be perform ed as required by the U F S A R s for each plant.

10 C F R 50, A ppendix A, G D C 4, "E nvironm ental and dynam ic effects design bases," provides requirem ents for certain system s to be able to w ithstand postulated events w ithout loss of function. C om pliance w ith G D C 4 is not im pacted by the relocation of details from the T S to the U F S A R for augm ented inservice inspection of high energy piping outside containm ent because the design basis for the affected piping is not changed by the relocation of inspection details to the U F S A R.

T he proposed T S changes are consistent w ith and in com pliance w ith the above regulatory requirem ents and criteria. T herefore, the proposed changes w ill assure safe operation by continuing to m eet applicable regulations and requirem ents.

4.2 P reced en t

T he S urry P ow er S tation license am endm ent request listed below requested the relocation of tw o T S containing augm ented inspection requirem ents from the T S to their T echnical R equirem ents M anual (T R M ). In addition, they added an augm ented inspection program description to the A dm inistrative C ontrols section of their T S. T he program description added to the A dm inistrative C ontrols provided a description of the augm ented inspection program that did not include detailed inform ation about how the program requirem ents w ere m et.

Letter from V irginia E lectric and P ow er C om pany to N R C, P roposed License A m endm ent R equest, R elocation of A ugm ented Inspection R equirem ents from T S 4.2 and T S 4.15 to T echnical R equirem ents M anual, dated A pril 11, 2014 (M L14112A 073)

Letter from N R C to V irginia E lectric P ow er C om pany, S urry P ow er S tation U nit N os 1 and 2, Issuance of A m endm ents R egarding R elocation of A ugm ented Inspection R equirem ents, dated A pril 28, 2015 (M L15099A 679)

E -7 Evaluation of Proposed Change

4.3 No Significant Hazard Consideration Determinati on Analysis

Southern Nuclear Operating Company (SNC) has evalua ted the proposed changes to the Technical Specifications (TS) using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazar ds consideration.

The proposed change will revise the Farley Nuclear Plant (FNP) TS by relocating some detailed information from TS 5.5.16, Main Steamline Inspect ion Program, to the FNP Updated Final Safety Analysis Report (UFSAR). The proposed chang e also revises the Vogtle Electric Generating Plant (VEGP) TS by relocating some detai led information from TS 5.5.16, MS and FW Piping Inspection Program, to the VEGP UFSAR. A program description will remain in TS 5.5.16 for both plants.

As required by 10 CFR 50.91(a), the SNC analysis of the issue of no significant hazards consideration is presented below:

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

Response: No

The proposed relocation of program details from TS 5.5.16 of each plant to their respective UFSARs is appropriate since these requirements do n ot satisfy the categories and criteria of 10CFR50.36(c), which specifies what items qualify f or inclusion in the TS. The augmented inspections, which are performed in addition to req uired ASME Code Section Xl inspections or examinations, will continue to be performed as requ ired by the UFSAR. The requirement to have an augmented inspection program remains in the TS. The plant systems and components to which the augmented inspections apply will not b e operated in a different manner. The proposed relocation of the augmented inspection det ails does not involve a physical change to the plant or a change to the manner in which the pl ant is operated or controlled.

Therefore, the proposed changes do not involve a si gnificant 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 changes do not alter the physical desi gn, safety limits, or safety analysis assumptions associated with the operation of the pl ant. As such, no new or different types of equipment will be installed, and the basic operatio n of installed plant systems and components, to which the augmented inspections apply, is unchan ged. Hence, the proposed changes do not introduce any new accident initiators, nor do these changes reduce or adversely affect the capabilities of any plant structure or system in th e performance of their safety function.

Therefore, the proposed changes do not create the p ossibility of a new or different kind of accident from any accident previously evaluated.

E-8 Evaluation of Proposed Change

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

Response: No

The proposed changes do not alter the manner in whi ch safety limits or limiting safety system settings are determined. The safety analysis accept ance criteria are not affected by these proposed changes. Further, the proposed changes do not change the design function of any equipment assumed to operate in the event of an acc ident.

The proposed changes will not reduce a margin of sa fety because the relocation of details of the augmented inspection program to the plants respect ive UFSARs has no impact on any safety analysis assumptions, as indicated by the fact that the requirements do not meet the 10CFR50.36(c) criteria for inclusion in the TS. In addition, the details of the augmented inspections will be moved to the UFSARs and will co ntinue to be performed as required by the UFSARs.

Therefore, the proposed change does not involve a s ignificant reduction in a margin of safety.

4.4 Conclusion

In conclusion, based on the considerations discusse d above, SNC concludes: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activiti es will be conducted in compliance with the Commissions regulations, and (3) the issuance of t he amendment will not be inimical to the common defense and security or the health and safet y of the public.

5.0 ENVIRONMENTAL CONSIDERATION

The proposed change would revise a requirement with respect to installation or use of a facility component located within the restricted area, as de fined in 10 CFR Part 20, and would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significa nt change in the types or significant increase in the amounts of any effluent that may be released of fsite, or (iii) a significant increase in individual or cumulative occupational radiation exp osure. Accordingly, the proposed change meets the eligibility criterion for categorical exc lusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impac t statement or environmental assessment need be prepared in connection with the proposed ch ange.

6.0 REFERENCES

1. NUREG 75/034 (aka NUREG 0117), Supplement No. 1 to the Safety Evaluation Report by the Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission in the Matter of Alabama Power Company, Joseph M. Farl ey Nuclear Power Plant Units 1 and 2.

2. NUREG 1137, Safety Evaluation Report Related to the Operation of Vogtle Electric Generating Plant, Units 1 and 2, dated June 1985

3. Final Policy Statement on Technical Specificatio n Improvements for Nuclear Power Reactors, 58 FR 39132, dated July 22, 1993

E-9 Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2

License Amendment Request to Relocate Augmented Pip ing Inspection Program Details from Technical Specifications to a Licensee Control led Document

Attachment 1a

FNP Proposed Technical Specification Changes (Marke d-up Pages)

Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.15 Safety Function Determination Program (SFDP) (conti nued)

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported s ystem's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compe nsatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurren t loss of onsite diesel generator(s), a safety function assumed in the acci dent analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) suppor ted by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in tur n supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the support system(s ) for the supported systems (a) and (b) above is also inopera ble.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, th e appropriate Conditions and Required Actions of the LCO in which the loss o f safety function exists are required to be entered. When a loss of safety f unction is caused by inoperability of a single Technical Specification s upport system, the appropriate Conditions and Required Actions to ente r are those of the support system.

5.5.16 Main Steamline Inspection Program The three main steamlines from the rigid anchor poi nts of the containment penetrations downstream to and including the main s team header shall be inspected. The extent of the inservice examinations completed during each inspection interval (IWA 2400, ASME Code, 1974 Edit ion,Section XI) shall provide 100 percent volumetric examination of circu mferential and longitudinal pipe welds to the extent practical. Th e areas subject to examination are those defined in accordance with ex amination category C-G for Class 2 piping welds in Table IWC-2520.

In accordance with the augmented inservice inspecti on program for high energy lines outside of containment, examinations o f welds in the main steam lines of each unit shall be performed to provide as surance of the continued

Farley Units 1 and 2 5.5-13 Amendment No. 203 (Unit 1)

Amendment No. 199 (Unit 2)

Programs and Manuals 5.5

integrity of the piping systems over their service lifetime. These requirements apply to welds in piping systems or portions of sys tems 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 designe d specifically to cope with such ruptures.

Farley Units 1 and 2 5.5-13 Amendment No. 203 (Unit 1)

Amendment No. 199 (Unit 2)

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2

License Amendment Request to Relocate Augmented Pip ing Inspection Program Details from Technical Specifications to a Licensee Control led Document

Attachment 1b

VEGP Proposed Technical Specification Changes (Mark ed-up Pages)

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 MS and FW Piping Inspection Program This program shall provide for the inspection of the four Main Steam and Feedwater lines from the containment penetration flued head outboard welds, up to the first five-way restraint. The extent of the inservice examinations completed during each inspection interval (ASME Code Section XI) shall provide 100%

volumetric examination of circumferential and longitudinal welds to the extent practical. This augmented inservice inspection is consistent with the requirements of NRC Branch Technical Position MEB 3-1, "Postulated Break and Leakage Locations in Fluid System Piping Outside Containment," November 1975 and Section 6.6 of the FSAR.

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 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.

5.5.17 Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Nuclear Energy Institute (NEI)

Topical Report (TR) NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008, as modified by the following exceptions:

1. Leakage rate testing for containment purge valves with resilient seals is performed once per 18 months in accordance with LCO 3.6.3, SR 3.6.3.6 and SR 3.0.2.

2. Containment personnel air lock door seals will be tested prior to reestablishing containment integrity when the air lock has been used for containment entry. When containment integrity is required and the air lock has been used for containment entry, door seals will be tested at least once per 30 days during the period that containment entry(ies) is (are) being made.

3. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified Vogtle Units 1 and 2 5.5-16 Amendment No. 197 (Unit 1)

Amendment No. 180 (Unit 2)

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2

License Amendment Request to Relocate Augmented Pip ing Inspection Program Details from Technical Specifications to a Licensee Control led Document

Attachment 2a

FNP Revised Technical Specification Pages

Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.15 Safety Function Determination Program (SFDP) (continued)

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

Farley Units 1 and 2 5.5-13 Amendment No. (Unit 1)

Amendment No. (Unit 2)

5.5.16 Main Steamline Inspection Program

In accordance with the augmented inservice inspection program for high energy lines outside of containment, examinations of welds in the main steam lines 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.

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2

License Amendment Request to Relocate Augmented Pip ing Inspection Program Details from Technical Specifications to a Licensee Control led Document

Attachment 2b

VEGP Revised Technical Specification Pages Programs and Manuals 5.5

5.5 Programs and Manuals (continued)

5.5.16 MS and FW Piping Inspection Program

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 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.

5.5.17 Containment Leakage Rate Testing Program

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Nuclear Energy Institute (NEI)

Topical Report (TR) NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008, as modified by the following exceptions:

1. Leakage rate testing for containment purge valves with resilient seals is performed once per 18 months in accordance with LCO 3.6.3, SR 3.6.3.6 and SR 3.0.2.

2. Containment personnel air lock door seals will be tested prior to reestablishing containment integrity when the air lock has been used for containment entry. When containment integrity is required and the air lock has been used for containment entry, door seals will be tested at least once per 30 days during the period that containment entry(ies) is (are) being made.

3. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief or alternative has been authorized by the NRC. At the discretion of the licensee, the containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities such as tendon testing, or during a maintenance/refueling outage.

(continued)

Vogtle Units 1 and 2 5.5-16 Amendment No. (Unit 1)

Amendment No. (Unit 2)