GO2-09-051, Initial License Written Examination Documentation

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Initial License Written Examination Documentation
ML091030158
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 03/23/2009
From: Oxenford W
Energy Northwest
To: Garchow S
NRC Region 4
References
ES-201-3, GO2-09-051
Download: ML091030158 (20)
v • d • e


Text

W. Scott Oxenford Columbia Generating Station P.O. Box 968. PE08 ENERGY Richland, WA 99352-0968 Ph. 509.377.4300 I F. 509.377.4150 NORTHWEST soxenford@energy-northwest March 23, 2009 G02-09-05 1 Stephen Garchow US. Nuclear Regulatory Commission Region IV 612 E Lamar Blvd, Suite 400 Arlington, TX 76011-4125

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 INITIAL LICENSE WRITTEN EXAMINATION DOCUMENTATION

Dear Mr. Garchow:

The Initial License Written Examination was given at Columbia Generating Station on March 13, 2009. The required Written Examination Performance Analysis including justification for changes to the exam is attached.

The Examination Security Agreement, ES-201-3, will be faxed to you as soon as all post-examination signatures are complete.

If you require additional information, please contact S Jerrow, Manager, Operations Training, at (509) 377-2497.

No new regulatory commitments are made in this letter.

eration & Chief Nuclear Officer

Attachment:

Written Exam Performance Analysis cc: w/o attachment NRC Resident Inspector - 988C

Columbia Written Exam Analysis Question I Wrong I Total Analvsis RO Exam # 8 7/11 Question is technically correct. Knowledge deficiency that CIA Header low pressure alarm actuates 3 minutes after condition exists. Review ARP with class. No program deficiency noted.

RO Exam # 40 6/11 Question is technically correct. Knowledge deficiency in the actual location on the SRV tailpipe and number of vacuum breakers per tailpipe. Review with class. No

pr RO Exam # 41 program deficiency noted.

Question is technically correct. Question answered only looking at FWLC and not the failure effect on plant.

Review with class. No program deficiency noted.

SRO Exam # 15 617 Question is technically correct. SGT swaps to lead fan running and original lineup incorrect. Review with class.

No program deficiency noted.

SRO Exam # 18 517 Question submitted for changing the correct answer from D to C.

SRO Exam # 20 517 Question submitted for dual credit as D is also correct.

~~ ~

SRO Exam # 25 417 Question is technically correct. Students that missed this question did not take into account the EAL declaration that needed to be made due to changing plant parameters. Review with class. No program deficiency noted.

SRO Exam Question #6 Columbia experienced a LOCA. When the Reactor was manually scrammed, all rods did not go in.

Reactor power is 2% and steady, Drywell Pressure is 12 psig and trending up slow and Suppression Pool temperature is 85°F and steady. The Shift Manager declares a Site Area Emergency.

Which of the following prompts the Shift Manager to declare a Site Area Emergency and what actions should the CRS direct?

A. Suppression Pool Level indicates 19 ft. 1 inch. Direct HPCS initiation per PPM 5.5.23.

d. Wetwell Pressure indicates 12 psig. Direct Drywell sprays be initiated per PPM 5.2.1.

C. RPV/L indicates -181. Enter PPM 5.1.5 and direct an Emergency Depressurization.

D. An ATWS exists. Enter PPM 5.1.2 and direct PPM 5.5.10 and PPM 5.5.11 to insert rods.

ANSWER: B

REFERENCE:

PPM 13.1.1 block3.1.S.l; PPM 5.2.1 JUSTIFICATION: The SAE is declared due to 3.1 .S.1 - Drywell pressure response not consistent with LOCA conditions as WW and DW pressures are almost equal. Normal dP is 5 psig. A is incorrect as a UE would be declared. C is incorrect as RPV/L would need to be -183 for SAE. D is incorrect as all the conditions for 2.2.S.1 are not met.

The stem gives parameters that indicate that Primary Containment is broken and drywell pressure GT 12 psig which requires drywell sprays be initiated. D is the correct answer per the exam key and is correct.

Choice A is also a correct answer. If you look at the stem and plot the parameters given on the PSP curve, you end up in the unsafe region of PSP therefore PSP has been exceeded. Based on exceeding PSP with drywell pressure GT 1.68 psig, with indication of RCS leakage inside drywell, a Site Area Emergency should be declared per EAL 3.2.S.2. Additionally, with Wetwell Level LT -2 inches, PPM 5.2.1 directs HPCS be used to refill the wetwell per PPM 5.5.23. This makes choice A also a correct answer.

Choice A was originally indicated to be incorrect based upon Wetwell Level not able to be maintained above 19 2 which, if you look at block L-7 for PPM 5.2.1 Primary Containment Control, indicates that a UE should be declared.

Columbia is requesting dual credit for answers Aand B for this question.

c **

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION ## 6 EXAM KEY JANUARY 2009 Columbia experienced a LOCA. When the Reactor was manually scrammed, all rods did not go in. Reactor power is 2% and steady, Drywell Pressure is 12 psig and trending up slow and Suppression Pool temperature is 85°F and steady. The Shift Manager declares a Site Area Emergency.

Which of the following prompts the Shift Manager to declare a Site Area Emergency and what actions should the CRS direct?

A. Suppression Pool Level indicates 19 ft. 1 inch. Direct HPCS initiation per PPM 5.5.23.

B. Wetwell Pressure indicates 12 psig. Direct Drywell sprays be initiated per PPM 5.2.1.

C. RFW5 indicates - 18 1. Enter PPM 5.1.5 and direct an Emergency Depressurization, D. An ATWS exists. Enter PPM 5.1.2 and direct PPM 5.5.10 and PPM 5.5.1 1 to insert rods.

a ANSWER: B

~ ~ ~~

QUESTION TYPE: SRO Closed KA # & KA VALUE: 295024 AA2.04 Ability to determine andor interpret the following as they apply to High Drywell Pressure: Suppression chamber pressure (3.9 / 3.9) 55.43.5

REFERENCE:

PPM 13.1.1 block 3.1.S.1; PPM 5.2.1 SOURCE: New LO: 613 1 With the procedures available for reference and plant conditions such that an emergency classification be declared, correctly classify the event.

RATING: H3 ATTACHMENT: Yes - PPM 13.1.1 blocks for 2.2.S.1; 3.1.S.1; 2.1.S.1; 3.2.U.1 JUSTIFICATION: The SAE is declared due to 3.1.S.1 - Drywell pressure response not consistent with LOCA conditions as WW and DW pressures are almost equal. Normal dP is 5 psig.

A is incorrect as a UE would be declared. C is incorrect as R P V 5 would need to be

- 183 for SAE.D is incorrect as all the conditions for 2.2.S. 1 are not met.

L-5 L-9 Maintain WW level as high as Maintain V possible above 19 ft. 2 in. S RVTPLL I

BEFORE L-IO W W level cannot be maintained above 19 ft 2 in.

Concurrently WHEN WW level w n o t A L-1 I be maintained UE above 19 ft 2 in.

L-12 Svstem WW Level (ft)

I IIf adequate stop injectic external to required to RCIC with siictinn frnm W W 17 S I L-13 /

Number: 13.1.1 Use Category: REFERENCE Revision: 36

Title:

CLASSIFYINGTHE EMERGENCY Page: 17 of 38 CATEGORY UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 3 PrimaryContaimnent 3.1 Primary Containment Pressure 1 2 3 1

2rywell pressur6 response not mnsistent with LOCA mnditions 1 2 3 1

Attachment 5.1, Columbia Generating Station Emergency Classification Table

SRO Exam Question # I 8 The plant is operating at 100% power. B RHR was declared inoperable yesterday at 0800 because of a ground on RHR-P-2Bs motor. During an A RHR Operability test, RHR-V4A, Suppression Pool suction valve, was closed, tripped on electrical overload mid-stroke, and was subsequently declared inoperable at 1200 today. Then at 1800 today, B RHR was declared operable.

Based on the above information, Columbia must be in MODE 3 no later than ...

A. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 2000 today.

B. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0200 tomorrow.

C. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0800 yesterday.

D. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 1200 today.

ANSWER: D

REFERENCE:

TS 3.6.1.5-1; TS 3.6.1.3-1 & -2; TS 3.5.1-1, -2 & -3; TS 3.6.2.3-1 JUSTIFICATION: At 0800 yesterday a 7 day clock started. At 1200 today the 7 day clock became a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock (2 spray systems 00s).At 1800 the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock stopped and again became a 7 day clock but clock is started from first RHR system failure (B RHR ground) and not A RHR (RHR-V-4A failure). A is incorrect as it is for 2 trains 00s from 1200 today; B is incorrect as it is todays time (1800) plus 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. C is incorrect as it is 7 days from the first RHR failure and does not take into account that the completion times may be extended per TS section 1.3. D is correct.

The stem states that RHR-B went hop yesterday at 0800, RHR-A went inop at 1200 today and then RHR-B was declared operable at 1800 today. Technical Specifications 1.3 (Completion Times) states that when a second division is discovered to be inop the completion time may be extended; and then it gives criteria necessary to extend the time.

The stem includes those conditions to extend the completion time. Technical Specifications then states that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be added to the initial entry into the condition.

If you add the extension onto the initial entry, Columbia must be in Mode 3 no later than 7 days (per TS 3.1.6.5), plus 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (extension per TS 1.3) plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (completion time to be in Mode 3 given by TS 3.6.1 5)from 0800 yesterday.

If you take the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension the completion time is 7 days plus 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0800 yesterday. Choice ID the original answer, is actually 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> too long which makes it an incorrect answer. Choice C is the correct answer as it is 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from the initial entry into the condition.

Columbia is requesting the answer to question #18 be changed from D to IC,

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION # 18 EXAM KEY MARCH 2009 The plant is operating at 100% power. B RHR was declared inoperable yesterday at 0800 because of a ground on RHR-P-2Bs motor. During an A RHR Operability test, RHR-V-4A, Suppression Pool suction valve, was closed, tripped on electrical overload mid-stroke, and was subsequently declared inoperable at 1200 today. Then at 1800 today, B RHR was declared operable.

Based on the above information, Columbia must be in MODE 3 no later than.. .

A. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 2000 today.

B. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0200 tomorrow.

C. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 0800 yesterday.

D. 7 days plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 1200 today.

ANSWER: D QUESTION TYPE: SRO Closed KA # & KA VALUE: 226001 A2.11 Ability to (a) predict the impacts of the following on the RHWLPCI:

Containment Spray Mode and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Motor operated valve failures (3.0 / 3.0) 55.43.2

REFERENCE:

TS 3.6.1.5-1; TS 3.6.1.3-1 & -2; TS 3.5.1-1, -2 & -3; TS 3.6.2.3-1 SOURCE: NEW LO: 5783 Referencing Columbias Technical Specifications associated with the RHR System and a set of plant conditions, determine as applicable the LSSS, the LCO, the action statement, and the bases.

RATING: H3 ATTACHMENT: Yes - TS I .3-1 and 1.3-2. TS 3.6.1.5-1; TS 3.6.1.3-1 & -2 TS 3.5.1-1, -2 and -3; TS 3.6.2.3-1 JUSTIFICATION: At 0800 yesterday a 7 day clock started. At 1200 today the 7 day clock became a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock (2 spray systems 00s).At 1800 the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock stopped and again became a 7 day clock but clock is started from first RHR system failure (B RHR ground) and not A RHR (RHR-V4A failure). A is incorrect as it is for 2 trains 00s from 1200 today; B is incorrect as it is todays time (1800) plus 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. C is incorrect as it is 7 days from the first RHR failure and does not take into account that the completion times may be extended per TS section 1.3. D is correct.

ECCS - O p e r a t i n g 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS ( E C C S ) AND REACTOR CORE ISOLATION COOLING

( R C I C ) SYSTEM 3.5.1 ECCS - O p e r a t i n g LCO 3.5.1 Each E C C S i n j e c t i o n / s p r a y subsystem and t h e A u t o m a t i c D e p r e s s u r i z a t i o n System ( A D S ) f u n c t i o n o f s i x s a f e t y / r e l i e f v a l v e s s h a l l be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 , e x c e p t ADS v a l v e s a r e n o t r e q u i r e d t o be OPERABLE w i t h r e a c t o r steam dome p r e s s u r e 5 150 p s i g .

ACTIONS CONDITION I REQUIRED A C T I O N COMPLETION TIME A. One low p r e s s u r e E C C S A. 1 R e s t o r e low p r e s s u r e 7 days injection/spray ECCS i n j e c t i o n / s p r a y subsystem i n o p e r a b l e . subsystem t o OPERABLE status.

8. H i g h P r e s s u r e Core 8.1 . V e r i f y by Immediately Spray (HPCS) System a d m i n i s t r a t i v e means inoperable. R C I C System i s OPERABLE when R C I C System i s r e q u i r e d t o b e OPERABLE.

8.2 R e s t o r e H P C S System 14 d a y s t o OPERABLE s t a t u s .

( con t i nued 1 Columbia G e n e r a t i n g S t a t i o n 3.5,l- 1 Amendment No. 4 4 - 9 9 187

C o m p l e t i o n Times 1.3 1.0 U S E AND APPLICATION 1.3 C o m p l e t i o n Times PURPOSE The p u r p o s e o f t h i s s e c t i o n i s t o e s t a b l i s h t h e C o m p l e t i o n Time c o n v e n t i o n and t o p r o v i d e g u i d a n c e f o r i t s use.

BACKGROUND L i m i t i n g C o n d i t i o n s f o r O p e r a t i o n (LCOs) s p e c i f y minimum r e q u i r e m e n t s f o r e n s u r i n g s a f e o p e r a t i o n o f t h e u n i t . The A C T I O N S a s s o c i a t e d w i t h an L C O s t a t e C o n d i t i o n s t h a t t y p i c a l l y d e s c r i b e t h e ways i n w h i c h t h e r e q u i r e m e n t s o f t h e LCO can f a i l t o be met. S p e c i f i e d w i t h each s t a t e d C o n d i t i o n a r e R e q u i r e d A c t i o n ( s 1 and C o m p l e t i o n T i m e ( s ) .

DESCR I P T I ON The C o m p l e t i o n Time i s t h e amount o f t i m e a l l o w e d f o r c o m p l e t i n g a Required A c t i o n . I t i s referenced t o the time o f d i s c o v e r y o f a s i t u a t i o n ( e . g . , i n o p e r a b l e equipment o r v a r i a b l e n o t w i t h i n l i m i t s ) t h a t r e q u i r e s e n t e r i n g an ACTIONS Condition unless otherwise specified, providing the u n i t i s i n a MODE o r s p e c i f i e d c o n d i t i o n s t a t e d i n t h e A p p l i c a b i l i t y o f t h e LCO. R e q u i r e d A c t i o n s must be completed p r i o r t o t h e e x p i r a t i o n o f t h e s p e c i f i e d C o m p l e t i o n Time. An A C T I O N S C o n d i t i o n r e m a i n s i n e f f e c t and t h e R e q u i r e d A c t i o n s a p p l y u n t i l t h e C o n d i t i o n no l o n g e r e x i s t s o r t h e u n i t i s n o t w i t h i n t h e LCO A p p l i c a b i l i t y .

I f s i t u a t i o n s are discovered t h a t r e q u i r e e n t r y i n t o more t h a n one C o n d i t i o n a t a t i m e w i t h i n a s i n g l e LCO ( m u l t i p l e C o n d i t i o n s ) , t h e R e q u i r e d A c t i o n s f o r each C o n d i t i o n must be p e r f o r m e d w i t h i n t h e a s s o c i a t e d C o m p l e t i o n Time. When i n m u l t i p l e C o n d i t i o n s , s e p a r a t e C o m p l e t i o n Times a r e t r a c k e d f o r each C o n d i t i o n s t a r t i n g f r o m t h e t i m e o f d i s c o v e r y o f the s i t u a t i o n that required entry i n t o the Condition.

Once a C o n d i t i o n has been e n t e r e d , subsequent d i v i s i o n s ,

subsystems, components, o r v a r i a b l e s e x p r e s s e d i n t h e C o n d i t i o n , d i s c o v e r e d t o be i n o p e r a b l e o r n o t w i t h i n l i m i t s ,

w i l l not r e s u l t i n s e p a r a t e e n t r y i n t o t h e C o n d i t i o n u n l e s s s p e c i f i c a l l y s t a t e d . The R e q u i r e d A c t i o n s o f t h e C o n d i t i o n c o n t i n u e t o a p p l y t o each a d d i t i o n a l f a i l u r e , w i t h C o m p l e t i o n Times based on i n i t i a l e n t r y i n t o t h e C o n d i t i o n .

However, when a subsequent d i v i s i o n , subsystem, component, o r v a r i a b l e e x p r e s s e d i n t h e C o n d i t i o n i s d i s c o v e r e d t o be i n o p e r a b l e o r n o t w i t h i n l i m i t s , t h e C o m p l e t i o n T i m e ( s ) may be e x t e n d e d . To a p p l y t h i s C o m p l e t i o n Time e x t e n s i o n , t w o c r i t e r i a must f i r s t be m e t . The subsequent i n o p e r a b i l i t y :

(continued)

C o l umbi a G e n e r a t i n g S t a t i o n 1.3-1 Amendment No. 4-44) 1691

C o m p l e t i o n Times 1.3 1.3 C o m p l e t i o n Times DE S C R I PT I ON a. Must e x i s t c o n c u r r e n t w i t h t h e f i r s t i n o p e r a b i l i t y ;

(continued) and

b. Must r e m a i n i n o p e r a b l e o r n o t w i t h i n l i m i t s a f t e r t h e f ir s t in o p e r a b i 1 it y is r e s o l ved.

The t o t a l C o m p l e t i o n Time a l l o w e d f o r c o m p l e t i n g a R e q u i r e d A c t i o n t o a d d r e s s t h e subsequent i n o p e r a b i l i t y s h a l l be l i m i t e d t o t h e more r e s t r i c t i v e o f e i t h e r :

a. The s t a t e d C o m p l e t i o n Time, as measured f r o m t h e i n i t i a l e n t r y i n t o t h e C o n d i t i o n , p l u s an a d d i t i o n a l 24 h o u r s ; o r
b. The s t a t e d C o m p l e t i o n Time as measured f r o m d i s c o v e r y o f t h e subsequent i n o p e r a b i l i t y .

The above C o m p l e t i o n Time e x t e n s i o n does n o t a p p l y t o t h o s e S p e c i f i c a t i o n s t h a t have e x c e p t i o n s t h a t a l l o w c o m p l e t e l y s e p a r a t e r e - e n t r y i n t o t h e C o n d i t i o n ( f o r each d i v i s i o n ,

subsystem, component, o r v a r i a b l e e x p r e s s e d i n t h e C o n d i t i o n ) and s e p a r a t e t r a c k i n g o f C o m p l e t i o n Times based on t h i s r e - e n t r y . These e x c e p t i o n s a r e s t a t e d i n i n d i v i d u a l Specifications.

The above C o m p l e t i o n Time e x t e n s i o n does n o t a p p l y t o a C o m p l e t i o n Time w i t h a m o d i f i e d " t i m e z e r o . " This modified

" t i m e z e r o " may be e x p r e s s e d as a r e p e t i t i v e t i m e ( i . e . ,

" o n c e p e r 8 h o u r s , " where t h e C o m p l e t i o n Time i s r e f e r e n c e d from a previous completion o f t h e Required A c t i o n versus t h e t i m e o f C o n d i t i o n e n t r y ) o r as a t i m e m o d i f i e d by t h e p h r a s e "from discovery . . .'I Example 1 . 3 - 3 i l l u s t r a t e s one use of t h i s t y p e o f C o m p l e t i o n Time. The 1 0 day C o m p l e t i o n Time s p e c i f i e d f o r C o n d i t i o n s A and B i n Example 1 . 3 - 3 may n o t be extended.

( con t inued 1 Columbia G e n e r a t i n g S t a t i o n 1.3-2 Amendment No. 4-43 1691

RHR D r y w e l l Spray 3.6.1.5 3.6 C O N T A I N M E N T SYSTEMS 3.6.1.5 R e s i d u a l H e a t Removal ( R H R ) D r y w e l l Spray LCO 3.6.1.5 Two RHR d r y w e l l s p r a y subsystems s h a l l be O P E R A B L E .

APPLICABILITY: MODES 1, 2 , and 3 .

ACT I O N S CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR d r y w e l l s p r a y A.l R e s t o r e RHR d r y w e l l 7 days subsystem i n o p e r a b l e . s p r a y subsystem t o OPERABLE s t a t u s .

B. Two R H R d r y w e l l s p r a y B. R e s t o r e one RHR 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> subsystems i n o p e r a b l e . drywell spray subsystem t o OPERABLE status.

C. R e q u i r e d A c t i o n and c. 1 Be i n MODE 3 . 12 h o u r s associated Completion Time n o t m e t , -

AND c.2 Be i n MODE 4 . 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Columbia G e n e r a t i n g S t a t i o n 3.6.1.5-1 Amendment No. 3-49 1691

ECCS - Operating 3.5.1 ACTIONS CONDITION REQUIRED A C T I O N COMPLETION T I M E C. Two ECCS i n j e c t i o n c.1 R e s t o r e one E C C S 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystems i n o p e r a b l e . in j e c t i o n / s p r a y subsystem t o O P E R A B L E OR status.

One ECCS i n j e c t i o n and one ECCS s p r a y subsystem i n o p e r a b l e .

D. R e q u i r e d A c t i o n and D. 1 Be i n MODE 3. 12 h o u r s associated Completion Time o f C o n d i t i o n A , -

AND B, o r C n o t met.

D.2 Be i n MODE 4. 36 h o u r s E. One r e q u i r e d ADS v a l v e E.l R e s t o r e ADS v a l v e t o 14 days inoperable. OPERABLE s t a t u s .

. One r e q u i r e d ADS v a l v e F.l R e s t o r e ADS v a l v e t o 72 h o u r s inoperable. OPERABLE s t a t u s .

AND OR One low p r e s s u r e E C C S F.2 R e s t o r e low p r e s s u r e 72 h o u r s in j e c t i o n / s p r a y ECCS i n j e c t i o n / s p r a y subsystem i n o p e r a b l e . subsystem t o OPERABLE status.

( c o n t i nued )

Columbia G e n e r a t i n g S t a t i o n 3.5.1-2 Amendment No. 4-49 169 I

ECCS - O p e r a t i n g 3.5.1 ACTIONS ~~ ~~

CON0 IT I O N REQUIRED ACTION COMPLETION T I M E G. Required A c t i o n and G. 1 Be i n MODE 3. 12 h o u r s a s s o c i a t e d Compl e t i on Time o f C o n d i t i o n E -

AND o r F n o t met.

G.2 Reduce r e a c t o r steam 36 h o u r s OR dome p r e s s u r e t o

< 150 p s i g .

Two o r more r e q u i r e d ADS V a l ves i n o p e r a b l e .

H. HPCS and Low P r e s s u r e H.l E n t e r LCO 3.0.3. Immediately Core Spray (LPCS)

Systems i n o p e r a b l e .

Three o r more E C C S injection/spray subsystems i n o p e r a b l e .

HPCS System and one o r more r e q u i r e d ADS valves inoperable.

Two o r more E C C S injection/spray subsystems and one o r more r e q u i r e d A D S v a 1 ves i nopera b l e .

Columbia G e n e r a t i n g S t a t i o n 3.5.1-3 Amendment No. 3-49 1691

PCIVs 3.6.1.3 3.6 CONTAINMENT S Y S T E M S 3.6.1.3 Primary Containment I s o l a t i o n Valves (PCIVs)

LCO 3.6.1.3 Each P C I V , e x c e p t r e a c t o r b u i l d i n g - t o - s u p p r e s s i o n chamber vacuum b r e a k e r s , s h a l l be OPERABLE.

APPLICABILITY: MODES 1, 2 , and 3, When a s s o c i a t e d i n s t r u m e n t a t i o n i s r e q u i r e d t o be O P E R A B L E p e r LCO 3.3.6.1, "Primary Containment I s o l a t i o n I n s t rumenta t ion. "

ACTIONS

1. P e n e t r a t i o n f l o w p a t h s may be administrative controls .
2. S e p a r a t e C o n d i t i o n e n t r y i s a lowed f o r each p e n e t r a t i o n f l o w p a t h .
3. E n t e r a p p l i c a b l e C o n d i t i o n s and R e q u i r e d A c t i o n s f o r systems made i n o p e r a b l e by P C I V s .
4. E n t e r a p p l i c a b l e C o n d i t i o n s and R e q u i r e d A c t i o n s o f LCO 3.6.1.1, "Primary C o n t a i n m e n t , " when P C I V l e a k a g e r e s u l t s i n e x c e e d i n g o v e r a l l c o n t a i n m e n t leakage r a t e acceptance c r i t e r i a .

CONDITION REQUIRED ACTION COMPLETION TIME

-~

A.l Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except penetration flow path f o r main steam by use o f a t l e a s t line one c l o s e d and d e - a c t i vated automatic valve, One o r more c l o s e d manual v a l v e , 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> f o r penetration flow paths b l i n d flange, o r m a i n steam l i n e w i t h one P C I V check v a l v e w i t h f l o w i n o p e r a b l e e x c e p t due through the valve t o leakage n o t w i t h i n secured.

limit.

AND (continued)

Col urnb i a Genera t i ng S t a t ion 3.6.1.3-1 Amendment No. 4-49 1691

PCIVS 3.6.1.3 ACT I O N S CONDITION REQUIRED A C T I O N COMPLETION T I M E A. (continued) A.2 --------NOTE---------

I s o l a t i o n devices i n h i g h r a d i a t i o n areas may b e v e r i f i ed by use o f a d m i n i s t r a t i v e means.

Verify the affected Once p e r penetration flow path 3 1 days f o r i s isolated. isolation devices outside primary containment Prior to e n t e r i n g MODE 2 o r 3 from MODE 4 i f primary c o n t a i n m e n t was d e - in e r t e d while i n MODE 4 , i f n o t performed w i t h i n the previous 92 days, f o r isolation d e v i ces in s i de p r imary containment

( c o n t i nued 1 Columbia G e n e r a t i n g S t a t i o n 3.6.1.3-2 Amendment No. "3 1691

RHR S u p p r e s s i o n Pool C o o l i n g 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 R e s i d u a l H e a t Removal (RHR) S u p p r e s s i o n P o o l C o o l i n g LCO 3.6.2.3 Two RHR s u p p r e s s i o n p o o l c o o l i n g subsystems s h a l l be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACT I O N S ~~ ~~

CONDITION REQUIRED A C T I O N COMPLETION T I M E A. One RHR s u p p r e s s i o n A.l R e s t o r e RHR 7 days pool cool i n g subsystem suppression pool in o p e r a b l e. c o o l i n g subsystem t o OPERABLE s t a t u s .

B. R e q u i r e d A c t i o n and 6.1 Be i n MODE 3. 12 h o u r s associated Completion Time o f C o n d i t i o n A -

AN0 n o t met.

6.2 Be i n MODE 4 . 36 h o u r s Two RHR s u p p r e s s i o n pool c o o l i n g subsystems i n o p e r a b l e Columbia G e n e r a t i n g S t a t i o n 3.6.2.3-1 Amendment No. H9 1691

SRO Exam Question #20 During the fuel shuffle in a refueling outage, as the Refueling Floor Supervisor, you observe a fuel bundle that doesnt seem to have the correct orientation. You review the NCTL and note the fuel bundles orientation is 180 degrees different from what the NCTL requires.

Which of the following is correct concerning this situation?

A. This is not considered to be a fuel loading error nor is it considered to be a reactivity event. The Refuel Floor Supervisor has the authority to correctly orientate the fuel bundle and will document the move on the NCTL.

B. This is considered to be a fuel loading error. The Refuel Floor Supervisor will correctly orientate the fuel bundle and document the move on the NCTL.

C. This is not considered to be a fuel loading error. This is considered to be a reactivity event which should be brought to managements attention.

D. This is considered to be a fuel loading error. The Reactivity Manager and the Shift Manager will determine how to resolve the error and must give permission to recommence the fuel shuffle.

ANSWER: C/)

REFERENCE:

PPM 6.3.2 Precaution and Limitation 5.25 page 15 JUSTlFICATION: Per PPM 6.3.2, the SM and Reactivity Manager are notified and will resolve error and give permission to recommence core alts (C is correct). The RFO does not have authority to resolve error alone (A is incorrect). Neither the CRS nor the Reactivity Manager alone gives permission to restart core alts (B and D are incorrect).

The question is written on the premise that the fuel bundle that the stem references as being mis-positioned, was moved during the current fuel shuffle. Under this premise, C is the correct answer.

The stem does not specifically state that the fuel bundle had been moved during this fuel shuffle.

Per SWP-ME-01 6.4, one of the definitions of a Fuel Loading error is A fuel bundle orientation in the reactor core is other than specified in the NCTL and not corrected prior to criticality.

If you take the premise that the fuel bundle was not moved during this fuel shuffle and was mis-orientated during the previous fuel shuffle and not corrected prior to criticality, than the event would be classified as a Fuel Loading Error which would lead to D being a correct answer.

Columbia is requesting dual credit be given for answers C and D for this question.

COLUMBIA GENERATING STATION SENIOR REACTOR OPERATOR WRITTEN EXAMINATION QUESTION ## 20 EXAM KEY JANUARY 2009 During the fuel shuffle in a refueling outage, as the Refuel'ingFloor Supervisor, you observe a fuel bundle that doesn't seem to have the correct orientation. You review the NCTL and note the he1 bundle's orientation is 180 degrees different from what the NCTL requires.

Which of the following is correct concerning this situation?

A. This is not considered to be a fuel loading error nor is it considered to be a reactivity event. The Refuel Floor Supervisor has the authority to correctly orientate the fuel bundle and will document the move on the NCTL.

B. This is considered to be a he1 loading error. The Rehe1 Floor Supervisor will correctly orientate the fuel bundle and document the move on the NCTL.

C. This is not considered to be a fuel loading error. This is considered to be a reactivity event which should be brought to managements attention.

D. This is considered to be a fuel loading error. The Reactivity Manager and the Shift Manager will determine how to resolve the error and must give permission to recommence the fuel shuffle.

ANSWER: C QUESTION TYPE: SRO Closed KA # & KA VALUE: 2.1.42Knowledge of new and spent fuel movement procedures (2.5/ 3.4) 55.43.7

REFERENCE:

PPM 6.3.2Precaution and Limitation 5.25 page 15 SOURCE: New LO: 8816 Given copies of plant procedures locate and demonstrate an understanding of the procedural "prerequisites, precautions and limitations" (Reheling).

RATING: L3 ATTACHMENT: None JUSTIFICATION: Per PPM 6.3.2, the SM and Reactivity Manager are notified and will resolve error and give permission to recommence core alts (C is correct). The RFO does not have authority to resolve error alone (A is incorrect). Neither the CRS nor the Reactivity Manager alone gives permission to restart core ah's (B and D are incorrect).

6.3 Reactivity Mananef - The individual with the primary responsibility for controlling core reactivity, and for assuring conservative actions are taken in response to a reactivity event.

6.4 -

Fuel Loadinn Errox A fuel loading error is defined as any of the following actions:

8 Inserting a fuel bundle in an incorrect location in the Reactor Cor. This point is reached when the nose piece of the bundle is inserted past the bottom of the Top Guide Core Structure in a location other than what is specified in the NCTL.

8 A fuel bundle orientation in the reactor core that is other than specified in the NCTL and nQl corrected prior to criticality. Any misorientation(s)should be reported to the Reactivity Manager as they are identified.

NOTE: Seating a fuel bundle in the SFP in a location or orientation other than specified in the NCTL is 9pt a fuel loading error.

6.5 Core Alt Suwrvisor (MAE) - The individual with the primary responsibility to supervise refuel activities involving core alterations. The position requires an SRO license per FSAR and 10CFR50.54.

6.6 SDent Fuel Pool Suwrvisor (RFAF) - The individual with the primary responsibility to supervise activities taking place in the Spent Fuel Pool, in other than mode 5, including movement of new fuel, spent fuel and other operations. This position does not require a NRC license.

7.0 REFERENCES

7.1 NOV 92-037-01-02, Manual Reactor Scram Due to Core Instability, June 18, 1993 { P-75586) 7.2 OER SOER96-02, Design and Operating Considerations for Reactor Cores.

{P-140619){ P- 140539) 7.3 PEW-297-0636, Mispositioned Control Rod { P- 143317) 7.4 Letter, IR-92-37-1, JV Parrish to USNRC, Response to Notice of Violations and Notice of Deviation - Power Oscillation Event, 01/11/93 7.5 Letter, IR-92-30, AL Oxsen to JB Martin, Response to NRC Augmented Inspection Report, 10/30/92 7.6 BWROG Reactivity Controls Committee Guidelines for Excellence b

NUMBER REVISION PAGE SWP-RXE-Ol 1 2a of 51

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