ML090690400
| ML090690400 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/25/2008 |
| From: | Operations Branch I |
| To: | Dominion Nuclear Connecticut |
| Hansell S | |
| Shared Package | |
| ML082600232 | List: |
| References | |
| 50-336/09-301, TAC U01634 50-336/09-301 | |
| Download: ML090690400 (44) | |
Text
OCT 0 2008 LicrrC RO UNIT INITIAL 55.40(b)(3),
1, until vide Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road, Waterford, CT 06385 3
Mr. Samuel L. Hansell, Jr., Chief Operations Branch, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Serial No.
MPS Docket No.
License No.
08-0606 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION 2
SENIOR REACTOR OPERATOR AND REACTOR OPERATOR EXAMINATIONS OUTLINE In a letter dated September 24, 2008,' the U.S. Nuclear Regulatory Commission (NRC) requested Dominion Nuclear Connecticut, Inc. submit the examination outline for the Senior Reactor Operator and Reactor Operator Initial Examinations - Millstone Power Station Unit 2, by November 3, 2008., Examination Outline, is being submitted to the NRC for review and approval. Pursuant to 10 CFR an authorized representative of the facility has approved the "complete and ready-to-use" examination outline contained in.
Consistent with guidance contained in NUREG-1 021 Examination Standard 201, Attachment "Examination Security and Integrity Considerations", the examination outline contained in Attachment 1 should be withheld from public disclosure after the examination has been completed. No redacted versions are being supplied.
Should you have any questions regarding this submittal, please contact Mr. Jeff T. Spence at (860) 437-2540.
Sincerely, Site President - Millstone 1 Samuel L. Hansell, Jr. letter from U.S. NRC, to David A. Christian, "Senior Reactor and Reactor Operator Initial Examinations - Millstone Unit 2," dated September 24, 2008.
Serial No. 08-0606 Senior Reactor Operator and Reactor Operator Initial Exarrrination Outline Page 2 of 2 Attachments:
1 Commitments made in this letter: None.
cc:
(W/O attachment)
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Ms. Carleen Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop 08B3 Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Serial No.08-0606 Docket No. 50-336 Examination Outline Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc. (DNC)
I.
- 11.
Systematic systemsltopics TierIGroup, th.e TierlGroup, systems/topics 111.
<2.5 2
Description of the Process Used to Develop the Millstone 2 Exam Outline Obtained copies of Forms ES-401-2, PWR Examination Outlines for SRO and RO, and Form ES-40 1-3 Generic Knowledge and Abilities Outline (Tier 3).
For each Tier and Group, the Example Sampling Methodology per ES-40 1, and guidance on ES-401-2 were used to select the topics for the RO exams as follows:
A.
Annotated all not applicable to Millstone 2 (Ex. W, BW).
B.
If a group had more topics than required for a tokens were then selected to randomly remove topics that would not be covered.
C.
If a group had less topics than required for a then tokens were randomly drawn to determine which topics would receive double question coverage.
D.
Selected the for the exam by randomly selecting tokens.
Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the WA categories for the RO and SKO exam for each topic.
IV.
Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the individual WA statements for the RO exam as follows:
A.
Any individual WA statement with an importance rating of was eliminated prior to the selection process.
B.
If a WA category had no importance rating 2.5, another WA category was randomly selected.
C.
Prior to randomly selecting the individual WA statements for Tier 1 and 2 "Generic"categories, non-relevant WA statements were removed.
V.
Verified each WA category for the RO exam had at least 2 points in each tier (as applicable).
VI.
Utilized the same process to generate the SRO outline as used for the RO outline.
However, duplicate WA topic that were already selected for the RO exam were rejected and randomly reselected per the Example Systematic Sampling Methodology per ES-40 1,.
1.?; 2008 Lic/TC CONNEC'I'ICUT, UNIT SENIOR REACTOR 2008,'
EngineerJChief 55.40(b)(3)
~ i 6 e Dominion Nuclear Connecticut, Inc.
Millstone Power Station Rope Ferry Road, Waterford, CT 06385 NOV Mr. Samuel L. Hansell, Jr., Chief Serial No.
08-0606A Operations Branch, Region I MPS RO U.S. Nuclear Regulatory Commission Docket No.
50-336 475 Allendale Road License No.
DPR-65 King of Prussia, PA 19406 DOMINION NUCLEAR INC.
MILLSTONE POWER STATION 2
OPERATOR AND REACTOR OPERATOR INITIAL WRITTEN EXAMINATIONS In a letter dated September 24, the U.S. Nuclear Regulatory Commission (NRC) requested Dominion Nuclear Connecticut, Inc. (DNC) submit the written examinations, operating tests, and supporting reference materials for the Senior Reactor Operator and Reactor Operator Initial Examinations - Millstone Power Station Unit 2, by December 1, 2008. In a telephone conversation between Mr. John G. Caruso, Senior Operations Examiner of the NRC and Mr. Michael J. Cote, DNC Supervisor Nuclear Training, the NRC requested that DNC submit the written examinations and supporting reference materials earlier, if possible. As agreed during the telephone conversation, DNC is submitting the written examinations and supporting reference materials by November 17, 2008. The operating tests will be provided by December 1, 2008., Written Examinations and Supporting Reference Materials, is being furnished in accordance with 10 CFR by an authorized representative of the facility.
Consistent with guidance contained in NUREG-1021 Examination Standard 201, Attachment 1, "Examination Security and Integrity Considerations", the written examinations and supporting reference materials contained in Enclosure 1 should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.
Should you have any questions regarding this submittal, please contact Mr. Jeff T. Spence at (860) 437-2540.
Sincerely, Site President - Millstone 1 Samuel L. Hansell, Jr. letter from U.S. NRC, to David A. Christian, "Senior Reactor and Reactor Operator Initial Examinations - Millstone Unit 2," dated September 24, 2008.
(W/O 08B3 AT-TN:
Serial No. 08-0606A Senior Reactor Operator and Reactor Operator Written Examinations Page 2 of 2
Enclosures:
1 Commitments made in this letter: None.
cc:
enclosure)
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Ms. Carleen Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
No.08-0606A Serial Docket No. 50-336 Written Examinations and Supporting Reference Materials Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc. (DNC)
will Serial No. 08-0606A This attachment contains highly confidential examination material which be attached to the letter by the training department following final sign-off.
2: 1 08-06066 LicrrC UNIT OPERATOR INITIAL 2008,'
Power 1,
EngineerIChief 1,
1, (JPMs),
10 55.40(b)(3)
NUREG-1021 1,
vice IVlillstone Dominion Nuclear Connecticut, Inc.
Millstone Power Station NOV 2008 Rope Ferry Road, Waterford, CT 06385 Mr. Samuel L. Hansell, Jr., Chief Serial No.
Operations Branch, Region I MPS RO U.S. Nuclear Regulatory Commission Docket No.
50-336 475 Allendale Road License No.
DPR-65 King of Prussia, PA 19406 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION 2
SENIOR REACTOR AND REACTOR OPERATOR WRITTEN In a letter dated September 24, the U.S. Nuclear Regulatory Commission (NRC) requested that Dominion Nuclear Connecticut, Inc. (DNC) submit the written examinations, operating tests, and supporting reference materials for the Senior Reactor Operator and Reactor Operator Initial Examinations - Millstone Station Unit 2, by December 2008.
In a telephone conversation between Mr. John G. Caruso, Senior Operations Examiner of the NRC and Mr. Michael J. Cote, DNC Supervisor Nuclear Training, the NRC requested that DNC submit the written examinations and supporting reference materials earlier, if possible. As agreed during the telephone conversation, DNC submitted the written examinations on November 17, 2008. Additionally, DNC is submitting the Job Performance Measures with this letter. The operating tests will be provided by December 2008.
Enclosure Job Performance Measures is being furnished in accordance with CFR by an authorized representative of the facility.
Consistent with guidance contained in Examination Standard 201, Attachment "Examination Security and Integrity Considerations", the written examinations and supporting reference materials contained in Enclosure 1 should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.
Should you have any questions regarding this submittal, please contact Mr. Jeff T. Spence at (860) 437-2540.
Sincerely, Site President - Millstone 1 Samuel L. Hansell, Jr. letter from U.S. NRC, to David A. Christian, "Senior Reactor and Reactor Operator Initial Examinations -
Unit 2," dated September 24, 2008.
(WIO 08B3 Serial No. 08-0606B Senior Reactor Operator and Reactor Operator Written Examinations Page 2 of 2
Enclosures:
1 Commitments made in this letter: None.
cc:
enclosure)
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. Carleen Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
No.08-0606B Measures (JPMsl Serial Docket No. 50-336 Job Performance Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc. (DNC)
08-06066 Serial No.
This attachment contains highly confidential examination material which will be attached to the letter by the training department following final sign-off.
NOV 5 2000 08-0606C LicITC UNIT INITIAL EngineerIChief The I,
10 55.40(b)(3)
/
~ i c ' e Dominion Nuclear Connecticut, Inc.
Millstone Power Station 2
Rope Ferry Road, Waterford, CT 06385 Mr. Samuel L. Hansell, Jr., Chief Operations Branch, Region I MPS RO U.S. Nuclear Regulatory Commission Docket No.
50-336 475 Allendale Road License No.
DPR-65 King of Prussia, PA 19406 DOMINION NUCLEAR CONNECTICUT. INC.
MILLSTONE POWER STATION 2
SENIOR REACTOR OPERATOR AND REACTOR OPERATOR WRITTEN In a letter dated September 24, 2008,' the U.S. Nuclear Regulatory Commission (NRC) requested that Dominion Nuclear Connecticut, Inc. (DNC) submit the written examinations, operating tests, and supporting reference materials for the Senior Reactor Operator and Reactor Operator Initial Examinations - Millstone Power Station Unit 2, by December 1, 2008.
In a telephone conversation between Mr. John G. Caruso, Senior Operations Examiner of the NRC and Mr. Michael J. Cote, DNC Supervisor Nuclear Training, the NRC requested that DNC submit the written examinations and supporting reference materials earlier, if possible. As agreed during the telephone conversation, DNC submitted the written examinations on November 17,2008, and the Job Performance Measures of the Operating Tests on November 21, 2008.
final portion of the Operating Tests, Simulator Scenarios, is being provided as an enclosure to this letter.
Enclosure Simulator Scenarios, is being furnished in accordance with CFR by an authorized representative of the facility.
Consistent with guidance contained in NUREG-1 021 Examination Standard 201, Attachment 1, "Examination Security and Integrity Considerations 7', the written examinations and supporting reference materials contained in Enclosure 1 should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.
Should you have any questions regarding this submittal, please contact Mr. Jeff T. Spence at (860) 437-2540.
Sincerely, Serial No.
Site president - Millstone 1 Samuel L. Hansell, Jr. letter from U.S. NRC, to David A. Christian, "Senior Reactor and Reactor Operator Initial Examinations - Millstone Unit 2," dated September 24, 2008.
Exaniinations (WIO 0883 Inspector Serial No. 08-0606C Senior Reactor Operator and Reactor Operator Written Page 2 of 2
Enclosures:
1 Commitments made in this letter: None.
cc:
enclosure)
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Ms. Carleen Sanders Project Manager U.S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop Rockville, MD 20852-2738 NRC Senior Resident Millstone Power Station U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
No.08-0606C Simulator Serial Docket No. 50-336 Scenarios Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc. (DNC)
will Serial No. 08-0606C This attachment contains highly confidential examination material which be attached to the letter by the training department following final sign-off.
$01 Exam:
11 il WA Ii !I
)I 11 ~ o t e :
outkes (i.e.,
I.
In "T~er nnust
!I
+I
,i 2
Systems/evolutions i:
br:
' i D.1.b regarding I /
. I t i I!
WAS SRt:)
I/
KIA KIAs Sectic~n D.1.b KIAs.
(IRs) jbove;
- I
- IRs, F3rrn
/ 1 KlAs
[I d
-2 PWR Examination Outline Form ES-Millstone Unit 2 Date of 02/02/09 RO Category Points SRO-Only Points
- 1.
Ensure that at least 2 topics from every KIA category are sampled within each tier of the RO and SRO 1
except for o e category Tier 3 of the SRO-only outline, the Totals" in each KIA category shall not be less than 2).
I!
- 2.
The point total for each group and tier in the proposed outline match those specified in the table.
The final point total for each group and tier may deviate by from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
within each group are identified on the associated outline; systems or evolutions that do not apply at the faci ty should be deleted and justified; operationally important, site-specific systemslevolutions that are included on the outline should added. Refer to Section of ES-401 for guidance the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting second topic for any system or evolution.
- 5.
Absent a plant specific, only those having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and categories.
- 7.
The generic in Tiers 1 and 2 shall be selected from 2 of the KIA Catalog, but the topics must be relevant to the app: cable evolution or system. Refer to Section of ES-401 for the applicable
- 8.
On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings for the appli able license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table if fuel handling equipment is sampled in other than A2 or G* on the SRO-only exam, enter it on the left side of column A2 for Tier 2 Group 2 (Note does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics form Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, and point totals (#) on ES-40103. Limit SRO selections to that are linked to 10 CFR 55.43.
ES-4.11-2 s,
ES-401 2
Form PWR Examination Outline following as they apply to the (Reactor Trip between the Reactor Coolant Pump Malfunctions failure modes, and automatic and manual organizations or external agencies, such as the State, the NRC, or the transmission system
ES-4\\11-2 itations Cateaorv ES-401 3
Form apply to the SGTR:
in the facility's license and nstrument Bus:
Feedwater pump speed to control pressure and level 00058 Loss of DC Power 16 A
Totals:
Group Point Total:
I 11 -2 ES-401 4
Form ES-4
11 -2 ES-401 5
Form ES-4
Form
ES401 11 -2 7
Form ES-4
11 -2 ES-401 8
Form ES-4
' ES-401 9
Form ES-4 31-2
01
/
MTIB TIG
-2 ES-401 Form ES-4--
System # Name s the apply to the System:
perature coefficient and boron centration in RCS as load or malfunction on the Fire tection System following will have system will have on the following:
ES. 401-3 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form Rejected due to lack of RO applicability.
ES-L I
Exam:
g -
WA Points 1)
II Note:
- 1.
(i.e.,
o.?e WA
+I
.from final 25 Systems/evolutions fac~
systems/evolutions be D.1.b WAS 1
WA II KIA aprlicable D.1.b KIAs.
WA (IRs)
- I RC)
I KIA and
- IRs,
=arm ES-401 PWR Examination Outline Form 01-2 Facility: Millstone Unit 2 Date of 02/02/09 RO Category SRO-Only Points Ensure that at least 2 topics from every WA category are sampled within each tier of the RO and SRO outlines except for category in Tier 3 of the SRO-only outline, the "Tier Totals" in each category shall not be less than 2).
- 2.
The point total for each group and tier in the proposed outline rnust match those specified in the table.
The final point total for each group and tier may deviate by that specified in the table based on NRC revisions. The RO exam must total 75 points and the SRO-only exam must total points.
- 3.
within each group are identified on the associated outline; systems or evolutions that do not apply at the ity should be deleted and justified; operationally important, site-specific that are included on the outline should added. Refer to Section of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant specific, only those having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SR3 ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and categories.
- 7.
The generic KlAs in Tiers 1 and 2 shall be selected from Section 2 of the Catalog, but the topics must be relevant to the evolution or system. Refer to Section of ES-401 for the applicable
- 8.
On the following pages, enter the numbers, a brief description of each topic, the topics' importance ratings for the app cable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than A2 or G* on the SRO-only exam, enter it on the left side of column A2 for Tie-2 Group 2 (Note does not apply). Use duplicate pages for and SRO-only exams.
- 9.
For Tier 3, select topics form Section 2 of the
- catalog, enter the KIA numbers, descriptions, and point totals (#) on ES-40103. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
1-2 ES EIAPE # I 1
K/A Topic(s) 1 16 ES-401 2
Form ES-4C Form 401-2 Name Safety Function procedures during abnormal and emergency 000009 Small Break LOCA 3 Rupture - Excessive Heat 000077 Generator Voltage and Electric Grid Disturbances
Form
Form
- I Name I Safety Function residual heat removal) mitigation
Form
Form
ES4rbl ES-401 7
Form
Form
- 2.
I conducting taste
/
MA T2/GI).
Generic Knowledge and Abilities Outline (Tier 3)
Form Facility: Millstone Unit 2 Date of Exam: 02/02/09 Category Topic RO I R levels.
\\
Equipment Control 2.2.7 Knowledge of the process for special or infrequent 3.6
- 3.
Radiation Control jeopardy" conflict with a previous selection (RO Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
KlAs I
Signzficance.
ofPZR LB-LOCA MP2.
i written due "doublejeopardy "
K/A T2iGI).
KIAs 211 due lack I
ES-401 Record of Rejected Form ES-401-4 Tier Randomly Reason for Rejection of Safety in a at 2.1.17 Rejected due to inability to test "verbal" skills on a exam.
2.3.6 Rejected to conflict with a previous selection (KO Rejected During Written Exam Development (Post-Outline Submittal) 000004 - K4.08 Rejected to luck of MP2 applicability.
RO R 0 3 2.2.17 Rejected due to o f RO applicability.
ES-401, Page :27of 33
(XI TY pe Procedures/Plan Rl N R'
Perfornl
[JPM-A1.2RI I
I I
[JPM-A1.3R-Spare]
i j
1
[JPM-A2R]
1-ocked
[JPM-A3RJ ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination:
Examination Level:
Administrative Topic Describe method of evaluation:
Code*
Conduct of Operations Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency R, M R, M R, D a Calculation for Boration to the RCS [JPM-A1.lR]
RO Determine Shutdown Margin RO Maximum RCS Venting Time Determination Calculate Time to Boil Review RWP and Survey Map for Entry into Tech Spec High Rad Area and Contaminated Area ES-301, Page 22 of 27
[XI r
Type P
'I
[JPM-A1.2SI
[.IPM-A1.IS]
I i
i
[JPM-A2S]
[JPM-A3S]
PARS [.IPM-A4S]
ProceduresIPlan ROs ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Examination Level:
RO Administrative Topic Conduct of Operations Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency SRO R, M R, M R, M R, D R, D S, N Date of Examination:
Operating Test Number:
Describe method of evaluation:
SRO Shift Staffing Requirements [JPM-SRO-SPARE]
SRO Perform a Shutdown Safety Assessment SRO Shift Turnover I
SRO Approve a Clearance Boundary SRO Review and Approve a Radioactive Liquid Waste Release Permit EAL Classification and Code*
I
& RO retakes) !
ES-301, Page 22 of 27
(XI SRO-W (XI I
JPlVl (GI, b
(GI,
- c.
(Gl,
- d.
S-I)
ROY
- f.
- 9.
h, Setpoint A, S, D, E, L A, S, E, L, D, A, S, E, N, L, A, S, M S, N A, S, D S, M A, S, D S, D 4(s) 1 4(p)
(RO,
- k.
R l
Dy E, L D, R E, N D, R 4(S)
/
/
<1=9 / <1=8 1 <1=4
>/=I /
/ >/=I
/
/ >/=I
>/=I / >/=I I
>/=I
>/=2 / >/=2 >/=I
</=3 / </=3 / <1=2
>/=I / >/=I / >/=I (A)lternate (C)ontrol (D)~rect (E)mergency in-(EN)gineered (L)ow-Power /
(N)ew (M)odified
~ncluding 1(A)
(P)revious 2 (R)CA (S)imulator 6(8)14(6)/2(4) 51515 1/1/1 41414 51412 O/O/O 1(2)11(2)11(2)/
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: Week of 01119109 Exam Level: RO SRO-I Operating Test No.:
Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System Title RO, S-I, S-U) Restore Letdown to Service RO, S-I, S-U) Swap 24C From "A" EDG to RSST RO, S-I, S-U) EOP-2541, App. 4, Start "A" Main Feed Pump (G2, RO, Force Pressurizer Sprays (G2, S-I) Failed Safety Channel NI (G2, KO, S-I) Start "B" Circulating Water Pump (G3, RO, S-I) RCP Seal Degradation and Failure (G3,RO, S-I) Shift CAR Coolers (Spare) Adjust Radioactive Waste Gas Radiation Monitor I.
Type Code*
EN Safety Function 2
6 3
7 8
5 9
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) j S-I, S-U) Local Manual Start of the Turbine Driven Auxiliary Feedwater Pump (KO, S-I, S-U) Shift Radioactive Waste Gas Decay Tanks I.
(RO, S-I, S-U) Place CEA on the Hold Bus (Spare) Local Manual Start of the "A" EDG 9
1 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Criteria for RO ISRO-IISRO-U 4-6 4-6 2-3
>I= 1 (control room system; 1
(randomly selected
- Type Codes:
Path room from bank of abnormal plant safety feature Shutdown or from bank exams Actual (with Spares) 61613 81712 (3 Available)
ES-301, Page 23 of 27
D ES08LI1 C$
gpm 24C, '6' Repairir~slreplacins 4.32:l.O qpm 24C, 'B' repairinglreplacinq
.l.b.
equi~ment RP19C CW04C FWOl NIA
'C' NI
'C' Waterbox (N)orrnal, (R)eactivity, (I)nstrurnent, (C)omponent, (M)ajor ES031 RCOGB NIA HPSl SlAS "B"
Appendix Scenario Outline Form ES-D-1 Facility:
MP2 Scenario No.:
Op-Test No.: 1 Examiners:
Operators:
Initial Conditions: 100% power, BOL. Eq. Xe., 1105 ppm Boron SGBD 40 per SG, 24E aligned to EDG OOS -
iniectors Turnover: 100% power, BOL, Eq. Xe., 1105 ppm Boron, blend ratio:
SGBD 40 per SG, 24E aligned to EDG OOS -
iniectors, in TSAS 3.8.1 No other OOS and no surveillance in progress or due Event No.
1 2
3 4
Event Type*
I C
C R, N Malf.
No.
Event Description RPS Lower Fails low Condenser Tube Leak Isolated condenser tube leak becomes vacuum leak Downpower due to vacuum leak 5
TC04 7
8 9
C M
N
'A' Pump failure to start on Stuck open PORV - LOCA..
Start " A SW Pump, Secure SW Pump Appendix D, 38 of 39
ES08L12 Eq.
apm ppm apm
- 24C, proqress D,
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NIA CW02C CV04A SGOlB NIA SG02B RXOIA chargiqg
- 2 to Appendix D Scenario Outline Form ES-D-1 Facility:
MP2 Scenario No.:
Op-Test No.: 2 Examiners:
Operators:
Initial Conditions: 100% power, BOL, Xe., 1105 ppm Boron SGBD 40 per SG, 24E aligned to 24C Turnover: 100% power, BOL, Eq. Xe., 1 105 SGBD 40 per SG, 24E aligned to surveillance in or due.
Boron, blend ratio: 4.32: 1.0 no equipment OOS and no Event No.
1 2
3 4
5 6
7 Malf.
No.
Event Type*
N C
C C
R, N M
C Event Description Swap CTMT penetration cooling fans C Traveling Screen DP high Running pump trips SGTL in SG Downpower due SGTL Steam generator tube rupture Main spray valve stuck open on trip Appendix 38 of 39
E S o 6 ~ i s
3 ES08LI No.:%
11 gpm
- 24C, replacement ppm 4.32:l.O gpm
- 24C,
. I
.I D,
I (N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NIA RD0328 N/A RX03B RD0132 EG08A FW30B FW20B
< 70%power Degradationlloss Scenario Outline Form ES-D-I Facility:
MP2 Scenario No.:
Op-Test Examiners:
Operators:
Initial Conditions: 100% power, BOL, Eq. Xe., 1105 ppm Boron SGBD 40 per SG, 24E aligned to TDAFP OOS for bearing Turnover: 100% power, BOL, Ea. Xe., 1105 Boron, blend ratio:
SGBD 40 per SG. 24E aligned to TDAFP OOS for bearing replacement, in TSAS 3.7.1.2.a and TRM '7.1 5, Table 7.1 5-1 A, B, C. No Event No.
1 2
3 4
5 6
7 8
Event Type*
N NIA C
R, N I
M C
C M
Malf.
No.
CH07 ED02 Event Description Pump containment sump Earthquake causing CEA #28 to slip 35 steps into the core.
Downpower to for CEA recovery Failure of Channel Y Pressurizer Pressure Instrument 2" dropped CEA Manual reactor trip RSST Fault - loss of off-site power A DG breaker failure to close of the 'B' AFW pump Appendix 38 of 39