ML16271A467

Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000498/2017007 and 05000499/2017007) and Request for Information

ML16271A467
Person / Time
Site:	South Texas
Issue date:	09/27/2016
From:	Greg Werner NRC/RGN-IV/DRS/EB-2
To:	Koehl D South Texas
References
IR 2017007
Download: ML16271A467 (10)

See also: IR 05000498/2017007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD

ARLINGTON, TX 76011-4511

September 27, 2016

Mr. Dennis Koehl

President and Chief Executive Officer

STP Nuclear Operating Company

P.O. Box 289

Wadsworth, TX 77483

SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNITS 1

AND 2 - NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION

BASELINE INSPECTION (NRC INSPECTION REPORT 05000498/2017007

AND 05000499/2017007) AND REQUEST FOR INFORMATION

Dear Mr. Koehl:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),

Region IV staff will conduct a triennial fire protection baseline inspection at the South Texas

Project Electric Generating Station, Units 1 and 2, in January and February 2017. The

inspection team will be comprised of four reactor inspectors from the NRC Region IV office.

The inspection will be conducted in accordance with Inspection Procedure 71111.05T, Fire

Protection (Triennial), the NRCs baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

• Information gathering visit: January 4-5, 2017

• On-site inspection: January 23-27, 2017

February 6-10, 2017

The purpose of the information gathering visit is to obtain information and documentation

needed to support the inspection and to become familiar with the fire protection program, fire

protection features, post-fire safe shutdown capabilities, plant layout, and mitigating strategies

to address Section B.5.b of NRC Order EA-02-026, Order for Interim Safeguards and Security

Compensatory Measures, dated February 25, 2002, and 10 CFR 50.54(hh)(2).

One inspector will participate in the information gathering visit to select the fire areas for

evaluation, identify additional documents needed to support the inspection, obtain unescorted

access, and meet with the key personnel who will support the inspection. The fire area

selection will require a walkdown of candidate fire areas in company with key personnel from

your staff. The enclosure to this letter provides an initial list of the documents the team will need

for their review. We request that your staff transmit copies of the documents listed in the

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enclosure to the NRC Region IV office for team use in preparation for the inspection. Please

send this information so that it will arrive in the NRC Region IV office by the dates listed in the

enclosure.

During the information gathering visit, the team will also discuss the following inspection support

administrative details: office space size and location, specific documents requested to be made

available to the team in their office spaces, arrangements for reactor site access, and the

availability of knowledgeable plant engineering and licensing organization personnel to serve as

points of contact during the inspection.

We request that during the on-site inspection weeks, you ensure that copies of analyses,

evaluations, or documentation regarding the implementation and maintenance of the fire

protection program, including post-fire safe shutdown capability, be readily accessible to the

team for their review. Of specific interest for the fire protection portion of the inspection are

those documents that establish that your fire protection program satisfies the NRC regulatory

requirements and conforms to applicable NRC and industry fire protection guidance. For

the B.5.b portion of the inspection, those documents implementing your mitigating strategies

and demonstrating the management of your commitments for the strategies are of specific

interest. Also, please ensure that appropriate personnel are available to support the team at the

site during the inspection. These personnel should be knowledgeable of the plant systems

required to achieve and maintain safe shutdown conditions from inside and outside the control

room, the electrical aspects of the post-fire safe shutdown analyses, the reactor plant fire

protection systems, and the fire protection program and its implementation.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget under control

number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice and Procedure, a copy of

this letter and its enclosure will be available electronically for public inspection in the NRC Public

Document Room or from the Publicly Available Records (PARS) component of NRC's document

system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

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Your cooperation and support during this inspection will be appreciated. If you have

questions concerning this inspection or the inspection team's information or logistical needs,

please contact Samuel Graves, the team lead inspector, in the Region IV office at

(817) 200-1102 or samuel.graves@nrc.gov.

Sincerely,

/RA/

Gregory E. Werner, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos. 50-498 and 50-499

License Nos. NPF-76 and NPF-80

Enclosure:

Triennial Fire Protection Inspection

Documentation Request

cc w/encl: Electronic Distribution

ML16271A467

SUNSI Review ADAMS Publicly Available Non-Sensitive Keyword:

By: SGraves Yes No Non-Publicly Available Sensitive NRC-002

OFFICE SRI:EB2 C:EB2

NAME SGraves GWerner

SIGNATURE /RA/ /RA/

DATE 9/15/16 9/27/16

Letter to Dennis Koehl from Gregory E. Werner, dated September 27, 2016

SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNITS 1

AND 2 - NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION

BASELINE INSPECTION (NRC INSPECTION REPORT 05000498/2017007

AND 05000499/2017007) AND REQUEST FOR INFORMATION

Electronic distribution by RIV:

Regional Administrator (Kriss.Kennedy@nrc.gov)

Deputy Regional Administrator (Scott.Morris@nrc.gov)

DRP Director (Troy.Pruett@nrc.gov)

DRP Deputy Director (Ryan.Lantz@nrc.gov)

DRS Director (Anton.Vegel@nrc.gov)

DRS Deputy Director (Jeff.Clark@nrc.gov)

Senior Resident Inspector (Alfred.Sanchez@nrc.gov)

Resident Inspector (Nicholas.Hernandez@nrc.gov)

Branch Chief, DRP/B (Nick.Taylor@nrc.gov)

Senior Project Engineer, DRP/B (David.Proulx@nrc.gov)

Project Engineer, DRP/B (Steven.Janicki@nrc.gov)

Administrative Assistant (Lynn.Wright@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Project Manager (Lisa.Regner@nrc.gov)

Team Leader, DRS/IPAT (Thomas.Hipschman@nrc.gov)

Project Engineer, DRS/IPAT (Eduardo.Uribe@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

ACES (R4Enforcement.Resource@nrc.gov)

Regional Counsel (Karla.Fuller@nrc.gov)

Technical Support Assistant (Loretta.Williams@nrc.gov)

Congressional Affairs Officer (Jenny.Weil@nrc.gov)

RIV Congressional Affairs Officer (Angel.Moreno@nrc.gov)

RIV/ETA: OEDO (Jeremy.Bowen@nrc.gov)

RIV RSLO (Bill.Maier@nrc.gov)

Triennial Fire Protection Inspection Documentation Request

Please provide the following documentation (Items 1-5) prior to the on-site information

gathering visit, preferably no later than December 19, 2016. Whenever practical, please provide

copies electronically in a searchable format. Please provide an index of the requested

documents which includes a brief description of the document and the numerical heading

associated with the request (i.e., where it can be found in the list of documents requested).

1. The current version of the fire protection program and fire hazards analysis.

2. Post-fire safe shutdown analysis and the supporting calculations that demonstrate

acceptable plant response.

3. Licensing basis documents for fire protection (safety evaluation reports, pertinent sections of

the final safety analysis report, exemptions, deviations, letters to/from the NRC regarding fire

protection/fire safe shutdown, etc.).

4. The fire probabilistic risk assessment or portions of the plants individual plant examination

for external events (IPEEE) report addressing fire events. Also, include the results of any

post-IPEEE reviews and listings of actions taken/plant modifications conducted in response

to IPEEE information that relate to fire risk.

5. A copy of the documents that support your multiple spurious operation evaluations (i.e.,

expert panel reports, evaluation packages, etc.).

Please provide the following documentation (Items 6 - 48) prior to the week of January 9, 2017,

to support inspection preparation. Whenever practical, please provide copies electronically in a

searchable format. Drawings should be provided as paper copies of sufficient size such that all

details are legible.

6. Plant layout and equipment drawings for fire areas that identify: (a) the physical plant

locations of major hot standby and cold shutdown equipment; (b) plant fire area and/or fire

zone delineation; (c) the locations of fire protection equipment, such as detection,

suppression, and post-fire emergency lighting units; and (d) fire area boundaries. The

specific documents needed to support inspection preparation will be discussed during the

site visit.

7. Fire protection program implementing procedures (e.g., administrative controls, operator

response procedures for fires, fire fighting procedures, etc.).

8. Operating procedures used for achieving and maintaining hot and cold shutdown conditions

from the control room in the event of a fire outside the control room (III.G.2 areas).

9. Operating procedures used to implement an alternative shutdown capability with or without

control room evacuation (III.G.3 areas).

10. A list of equipment used to achieve and maintain hot standby and cold shutdown in the

event of a fire (safe shutdown equipment list).

Enclosure

11. Piping and instrumentation (flow) diagrams showing the components used to achieve and

maintain hot standby and cold shutdown for normal and alternative shutdown. Please

provide one copy of the piping and instrumentation (flow) diagrams for these systems of a

size sufficient to read all details. These should include the systems used for reactor coolant

system makeup, reactor coolant system pressure control, decay heat removal, and reactivity

control, including the essential support systems.

12. A listing, with descriptions, of design change packages performed since the last triennial fire

protection inspection which were determined to impact fire protection and post-fire safe

shutdowns.

13. Fire protection program change evaluations (Generic Letter 86-10 evaluations) performed

since the last triennial fire protection inspection.

14. Procedures/instructions that control the configuration of the plants fire protection program,

features, and post-fire safe shutdown methodology and system design. Also,

procedures/instructions that govern the implementation of plant modifications, maintenance,

and special operations and their impact on fire protection.

15. A listing of open and closed corrective action documents initiated since the last triennial fire

protection inspection which relate to the fire protection program or equipment, including

corrective actions for fire-induced circuit failures (both single and multiple spurious

actuations) for the selected fire areas. Include the corrective action program document

number, date, and subject.

16. A listing of the applicable codes and standards (with the versions/dates) related to the

design of plant fire protection features and evaluations of any code deviations. Copies of

these codes should be available for review.

17. Drawings of the portions of the emergency lighting system which support fire response.

18. Procedures used to remove smoke from safety-related areas and the engineering studies or

calculations which support the design basis.

19. Drawings of communication systems credited in the license basis for firefighting and plant

operations during fires where control room is occupied and/or evacuated.

20. Piping and instrumentation (flow) diagrams for the fire water and sprinkler systems.

21. A listing of maintenance and surveillance testing procedures for alternative shutdown

capability and fire barriers, detectors, pumps and suppression systems. Also, include a list

of maintenance and surveillance testing procedures which verify fuse and breaker

coordination in accordance with the post-fire safe shutdown coordination analysis.

22. Maintenance rule performance criteria and a summary of the performance history for

systems or functions monitored within the maintenance rule program that support the fire

protection program or involve safe shutdown equipment over the period since the last

triennial fire protection inspection.

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23. Fire protection program requirements (e.g., limiting conditions for operation, surveillance test

requirements) covered by technical specifications, the technical requirements manual, the

updated final safety analysis report, or similar documents.

24. Internal and external self-assessments, audits, peer-assessments, or similar reviews related

to post-fire safe shutdown capability or the fire protection program completed since the last

triennial fire protection inspection.

25. A list of manual actions taken outside the control room which are credited to mitigate the

consequences of fires in III.G.2 areas (non-alternative shutdown areas). The list should

group actions by the initiating fire area or zone and indicate where the action must take

place.

26. Electronic copies of operator study guides (i.e., lesson plan text and graphics) or design

basis documents that describe the purpose/function/operating characteristics of the safe

shutdown systems (reactor coolant system makeup, reactor coolant system pressure

control, decay heat removal, and reactivity control, including the essential support systems).

27. Two copies of one-line diagrams of the AC and vital DC electrical distribution systems.

These should depict how power gets from the switchyard to the engineered safety feature

loads (480V and 4160V).

28. A list of automatic and manually initiated gaseous fire suppression systems in the plant,

giving their location and the key equipment being protected.

29. A list of repairs (and the procedure that controls the repairs) needed to reach and/or

maintain hot or cold shutdown.

30. A list of high to low pressure interface valves.

31. Procedures governing the training and operation of the fire brigade.

32. Organization charts of site personnel down to the level of fire protection staff personnel.

33. A contact list of key site personnel who will be supporting this inspection, giving the office

location and phone number onsite.

34. The team would like to observe an unannounced fire brigade drill in the plant, if possible,

during the week of February 6, 2017. Please put us in contact with the appropriate

personnel for planning fire brigade drills during the onsite information gathering trip.

35. The team would like to perform a walkthrough of the alternative shutdown procedure with

qualified operators in the plant during the week of January 23, 2017. The team would like to

perform a walkthrough of a sample of manual actions required for other fires not requiring

control room evacuation. Please put us in contact with the appropriate personnel for

planning the walkthroughs during the onsite information gathering trip.

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The following documents (Items 36 - 48) involve 10 CFR 50.54(hh)(2) mitigating strategies.

36. License condition that incorporated the requirements issued to address the requirements of

Section B.5.b of NRC Order EA-02-026, Order for NRC Interim Safeguards and Security

Compensatory Measures, dated February 25, 2002, and 10 CFR 50.54(hh)(2).

37. A list of all modifications to regulatory commitments made to meet the requirements of

Section B.5.b of NRC Order EA-02-026, Order for NRC Interim Safeguards and Security

Compensatory Measures, dated February 25, 2002; the subsequently imposed license

conditions; and 10 CFR 50.54(hh)(2).

38. A list of procedures/guidelines which were revised or generated to implement the mitigation

strategies. These could be extensive damage mitigation guidelines, severe accident

management guidelines, emergency operating procedures, abnormal operating procedures,

etc.

39. A matrix that shows the correlation between the mitigation strategies identified in Nuclear

Energy Institute 06-12 and the site-specific procedures or guidelines that are used to

implement each strategy.

40. A list of engineering evaluations/calculations that were used to verify engineering bases for

the mitigation strategies.

41. Piping and instrumentation diagrams or simplified flow diagrams for systems relied upon in

the mitigation strategies. These could be the type used for training.

42. A list of modification packages and simplified drawings/descriptions of modifications that

were made to plant systems to implement the mitigation strategies.

43. Procedures used to inventory equipment (hoses, fittings, pumps, etc.) required to be used to

implement the mitigation strategies.

44. A list of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details that differ

from that documented in the submittals to the NRC and the safety evaluation report.

45. Site general arrangement drawing(s) that show the majority of buildings/areas referenced in

B.5.b documents.

46. Training records and lesson plans related to the 10 CFR 50.54(hh)(2) mitigating strategies.

47. Copies of Memoranda of Understanding (MOUs) (e.g., with local fire departments) required

to implement any mitigating strategies.

48. The team would like to perform a walkthrough of the procedure implementing a sample

mitigating strategy (to be selected by the inspector during the information gathering visit)

and the inventory equipment (hoses, fittings, pumps, etc.) required to be used to implement

the mitigation strategies during the week of February 6, 2017. Please put us in contact with

the appropriate personnel for planning the walkthrough during the onsite information

gathering trip.

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The following documentation needs (Items 49 - 52) will be dependent upon sample selections

and will be finalized during discussions with your staff. Please provide the required documents

prior to the week of January 9, 2017. Whenever practical, please provide copies electronically

in a searchable format. Drawings should be provided as paper copies of sufficient size such

that all details are legible.

49. Pre-fire plans for the selected fire areas (areas to be selected by the team during the onsite

information gathering trip).

50. List of identified fire-induced circuit failure configurations that could prevent operation or

cause maloperation of equipment credited for safe shutdown in the event of a fire (for the

selected fire areas). Include failure configurations associated with hot shorts, open circuits,

or shorts to ground identified as potentially causing spurious or multiple spurious actuations

or maloperations of this equipment.

51. Cable routing information for components and equipment credited for safe shutdown in the

selected fire areas. This information request item will be discussed and finalized with your

staff during the information gathering visit.

52. Drawings showing the location details for detection and suppression systems in the selected

fire areas.

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