ML20210U758

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Rev 0 to Control Room Ventilation Radiation Monitors
ML20210U758
Person / Time
Site: Beaver Valley
Issue date: 05/29/1986
From: Frederick K, Kurtz E, Nass S
DUQUESNE LIGHT CO.
To:
Shared Package
ML20210U721 List:
References
DCP-711, DCP-711-R, DCP-711-R00, NUDOCS 8702180579
Download: ML20210U758 (10)
v • d • e


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DESIGN CONCEPT DCP No. 711 REV.-0 e

ATTACHMENT 2 PAGE 1 0F 6 C0ffrROL ROON VENTILATION RADIATION MONITORS TABLE OF CONTENTS Section Description Page 1.0 DESIGN OBJECTIVE ............................................ 2 2.0 BOUNDARIES OF THE CHANGE .................................... 2 3.0 COMPONENT MODIFICATIONS IMPORTAlfr TO SAFETY . . . . . . . . . . . . . . . . . 2 4.0 PRELIMINARY DESIGN INPITIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5.0 DESIGN APPROACH ............................................. 4 -

6.0 PRELIMINARY DESIGN OUTPUTS .................................. 5 7.0 HUMAN FACTOR ENGINEERING .................................... 5 8.0 FIRE PROTECTION CONSIDERATIONS .............................. 6 9.0 ENVIRONMENTAL QUALIFICATION ................................. 6 10.0 INSERVICE INSPECTION ........................................ 6 11.0 ALARA CONSIDERATIONS .................... ................... 6 12.0 PRELIMINARY COST ESTIMATE ................................... 6 13.0 SAFETY EVALUATION ........................................... 6 5

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De2ign C:necpt DCP 711-R v. 0

. Page 2 of 6 1.0 DESIGN OBJECTIVE During the licensing review of BVPS Unit 2, the NRC Accident Evaluation Branch directed Unit 2 to re-evaluate the control room habitability following accidents that would release radioactivity but would not initiate a CIB signal to isolate the control room. Stone and Webster Engineering Corporation performed this reanalysis and the results concluded that the 30 day thyroid dose to personnel in the control room would exceed the 10 CFR 50, GDC 19 limits for the following accidents, unless the control room was isolated and switched over to emergency ventilation; fuel handling accident, steam generator tube rupture, rod ejection accident, and a main steam line break. In order to resolve this licensing issue, Confirmatory Item No. 27 in Table 1.4 of the Final Draft SER (originally Draft SER Open Item No. 53), DLC has committed to providing redundant, Category I, area radiation monitors on both the Unit 1 and Unit 2 sides of the control room, before they remove the existing separation vall and it becomes a common facility.

The purpose of this modification is to provide two (2) redundant, Category I, seismic, Class IE gamma area radiation monitors for the Unit i side of the control room. These monitors will, upon a high radiation signal, initiate control room isolation (close outside dampers, initiate bottled air, and start the emergency supply fans one hour after receipt of signal) in order to maintain the dose, to personnel in the control room, below the GDC 19 limits.

2.0 BOUNDARIES OF THE CHANGE The boundaries of this design change include the Unit 1 control room structure and the Unit 1 Radiation Monitoring System. This modification vill also interface with the Control Room Emergency Bottled Air Pressurization System (CREBAPS).

3.0 COMPONENT MODIFICATIONS IMPORTANT TO SAFETY All modifications made under this design change vill be 0.A. Category I, Safety Related.

4.0 PRELIMINARY DESIGN INPtfrS i

4.1 SVEC letter to DLC, No. 2DLS-23867, Dated 12/19/84.

j 4.2 DLC letter No. 2NCD-04613, Dated 2/13/85.

4.3 BVS-414, " Specification for Radiation Monitoring System for BVPS Unit No. 1".

4.4 2BVS-509A, " Specification for Digital Radiation Monitoring System for BVPS Unit No. 2".

4.5 8700-RB-2D-19, " Flow Diagram - Vent & Air Cond. - Secondary l Plant, SH.2".

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.. Design Crnespt.

DCP 711 R;v. 0

, Page 3 of 6 4.6 8700-RM-3M-3, " Combined Control Room - Plan & Elevation".

3 4.7 8700-RB-17J-8, " Air Conditioning - Plan-SH.9, Control Room -

Service Bldg.".

4.8 8700-7.503-0110, Victoreen Technical Manual.

1 4.9 10 CFR 50, Appendix A, GDC 19.

4.10 10 CFR 50, Appendix R.

4.11 DLC letter No. ND2SHP:340, Dated 10/15/84.

4.12 DLC letter to SVEC, No. 2DLC-8601, Dated 4/2/85.

l. 4.13 DLC letter to USNRC, No. 2NRC-5-117, Dated 8/14/85.

l 4.14 NEDII-39, " Human Factors Engineering, Rev. O. -

3 4.15 IEEE 279-1971, " Protection Systems for Nuclear Power Generating Stations".

4.16 IEEE 323-1974, " Qualifying Class IE Equipment for Nuclear Power Generating Stations" 4.17 IEEE 344-1975, " Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations".

4.18 IEEE 384-1981, " Criteria for Independence of Class IE Equipment and Circuits".

4.19 BVS-3000, " Endorsement Specification for Electrical Work for Continuing Service Tasks".

1 4.20 BVS-3001, " Endorsement Specification for Criteria for.

Installation and Identification of Electrical Cables for Continuing Service Tasks".

4.21 BVPS Unit 1 Updated FSAR, Appendix B, Section B.2.24,

" Specification Requirements".

4.22 BVPS Unit 1, Updated FSAR, Section 11.3, " Radiation Protection-Shielding and Monitoring".

4.23 Nuclear Group Directives No. 20. " Occupational Radiation Exposure Reduction", Issue 2, 2/25/85.

4.24 Site Administrative Procedure, Chapter 23, " Occupational Radiation Exposure Reduction", Rev. 1, 7/31/85.

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Design C:ncspt DCP 711

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  • Page 4 of 6

. 4.25 USNRC Regulatory Guide .1.75, Rev. 2, September,1978.

4.26 USNRC Regulatory Guide 1.89, Rev. 1, June, 1984.

4.27 USNRC Regulatory Guide 1.100, Rev.1, August, 1977.

4.28 USNRC Regulatory Guide 8.8, Rev. 3, June, 1978.

4.29 USNRC Regulatory Guide 8.10, Rev. 1-R, May, 1977.

4.30 NEDII-30, "ALARA Reviews of Design Change Packages, Rev. 0 4.31 NEDII-31, " Appendix R Review of Design Change Packages", Rev. 0 4.32 DLC Fire Protection Appendix R Review Report for BVPS Unit #1.

4.33 BVPS Operating Manual, " Alternate Safe Shutdown Procedure",

Chapter 56C. -

4.34 Nuclear Engineering Memorandum, EM No. 72301 4.35 Nuclear Engineering Memorandum, EM No. 72302 5.0 DESIGN APPROACH 5.1 This modification vill purchase two (2) Category I, seismic, Class IE, gamma area radiation monitors, consisting of G-M tube detectors, ratemeters, interfacing cables, and mounting brackets.

5.2 The detectors shall be seismically mounted inside of the control room, such that their location vill provide them with a

, representative sample of the air discharged from the linear air ducts on the Unit 1 side of the control room.

5.3 The sensitivity of the monitors shall be lov enough such that the monitors are capable of performing the required function of timely isolation of the control room based on the alarm setpoints of SVEC Letter No. 2DLS-23867, and also be able to preclude the initiation of CREBAPS from spurious signals. A 4

minimum sensitivity of 0.01 mR/hr has been determined to meet these requirements.

5.4 The ratemeters shall be equipped to provide contact outputs for high alarm and fail alarm conditions and a contact to initiate CREBAPS. They should also be capable of providing outputs compatible with the existing radiation monitoring annunciator, computer, and recorders.

Dealgn C:nespt.

DCP 711

-. R;v. O Page 5 of 6 6.0 PRELIMINARY DESIGN OUTPUTS 6.1 Elementary Diagrams 6.2 Viring Diagcams 6.3 Conduit Diagrams 6.4 System Description and Logic Diagrams 6.5 Cable and Raceway Input Sheets 6.6 Support Drawings 6.7 Vendor Drawings 6.8 Vendor Documents 6.9 Purchase Specification 6.10 Construction and Installation Specification 6.11 Test Specification 6.12 Bill of Materials 6.13 Design Verification Documents 6.14 Recommended Spare Parts List 6.15 UFSAR Changes 6.16 Technical Specification Changes 6.17 Master Equipment List Changes 6.18 Engineering Change Notices 7.0 HUMAN FACTOR ENGINEERING 7.1 This modification vill install the detectors on the control room ceiling out of the way of the operators path for control board operation. It will also install the ratemeters into existing spare RMS racks and vill provide vertical board annunciation via the existing common radiation monitor annunciators.

Additionally, it will tie-in to the existing recorders and plant computer, if deemed necessary by RADCON.

7.2 A Human Factors Engineering Review vas initiated in accordance with NEDII-39 for the following control room features:

7.2.1 Annunciators 7.2.2 Controls 7.2.3 Visual Displays ,

7.2.4 Labels and Location Aids  !

7.2.5 Process Computers l 7.2.6 Panel Layout

Design C:ncspt DCP 711

  • R2v. 0 Page 6 of 6 8.0 FIRE PR&fBCTION CONSIDERATIONS Since this modification vill initiate CREBAPS 'and isolate the normal control room ventilation upon receipt of a high radiation alarm signal, it indirectly effects ventilation systems and therefore requires an

' Appendix R review.

9.0 ENVIRONMENTAL QUALIFICATION The Class IE radiation monitors will be environmentally qualified to meet IEEE 323-1974 and IEEE 344-1975 for the control room conditions.

10.0 INSERVICE INSPECTION This modification vill not impact the ISI or IST programs, since there are no pressure retaining components involved.

11.0 ALARA CONSIDERATIONS '

11.1 By making this modification, control room personnel vill stay below the 10 CFR 50, Appendix A, GDC 19 dose limits.

11.2 During the installation of this modification there vill be no ALARA concerns, since it will be located inside the control room, a clean area.

12.0 PRELIMINARY COST ESTIMATE Engineering $ 25,000 Construction 50,000 Haterial 55,000 Fringes 7,000 Overhead 14,000 AFFUDC 5,000 Total costs $156,000 13.0 SAFETY EVALUATION See attached Safety Evaluation Report for Design Concept No. 711.

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DUQUESNE LIGHT COMPANY NUCLEAR GROUP Nuclear Engineering and Construction Unit Station: Beaver Valley Unit No. 1 System: Radiation Monitoring Equipment: Control Room Area Monitors Equipment Nos:

DCP: 711, Dated 4-21-86, Rev. 0 , Account C0 4946 DESCRIPTION AND PURPOSE OF CHANGE This design change vill install two area radiation monitors in the Unit 1 control room. The detectors vill be mounted from the ceiling and tie in to the existing RMS rack. A high radiation signal from these monitors vill -

initiate control room isolation, bottled air and emergency supply fans after one hour.

The purpose of this modification is to maintain the dose to the personnel in the control room belov GDC 19 limits. This vill resolve a Unit 2 licensing issue.

CONCLUSION - SAFETY EVALUATION This design change is safe and does not present an unreviewed safety question. No new accidents are created and the probability of a malfunction of equipment is not increased. The margin of safety as defined in the applicable Technical Specifications bases is not reduced. A change to the UFSAR is required. A change to the Technical Specifications is required only to incorporate operability and surveillance requirements for the new monitors.

IRetEVIEVED SAFETY QUESTION DETERMINATION

1. Is the probability of an occurrence or the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the Updated Final Safety Analysis Report (FSAR) increased?

EE-REASON: The addition of these area radiation monitors will not increase the probability of any accident or malfunction evaluated in the UFSAR. The monitors vill be installed to withstand seismic events and without loss of function or affecting any connecting systems. The monitors will supply-a trip signal to the Control Room Pressurization System as described in Section 9.13.4 of the UFSAR. The trip point will be set to provide a low probability of spurious actuation.

2. Is the possibility-for an accident or malfunction of a different type than previously evaluated in the Updated Final Safety Analysis Report created? NO.

REASON: No new accidents are created by the installation of these radiation monitors, the probability of a malfunction of the Control Room Pressurization System caused by the failure or spurious actuation of these monitors is very lov based on the -

. trip setpoint, the Category I installation, and the component redundancy.

3. Is the margin of safety as defined in the basis for any technical specification reduced? NO.

REASON: The margin of safety as defined in the bases of Technical Specification 3/4.3.3 and 3/4.7.7 is not reduced. The additional monitors vill enhance the capability of the control room operators to perform during an accident.

4. Based on the above, is an unreviewed safety question involved? NO.
5. Is a change to the Updated FSAR required? YES.
6. Is a change to the Technical Specifications required? YES.

An addition to the Technical Specifications should be made to cover operability and surveillance requirements for the new monitors (See reference 9).

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l OA CATEGORY REVIEV

1. Q.A. Program Appendices Appendix A: The control room area radiation monitors are necessary for mitigation of the consequences of. certain accidents. These monitors therefore fit the definition of Category I.

Appendix B: The Main Control Room Monitor is listed as a Category I component.

Appendix C: N/A

2. Updated FSAR, Appendix B.

The Main Control Room Area itadiation Monitor (Existing) is listed as a component requiring design for seismic loading.

3. Master Equipment List The existing Main Control Room Monitor (RM-RM-213) is listed as non-safety related on the M.E.L.

QA CATEGORY CONCLUSION The new control room area radiation monitors shall be QA Category I, Seismic.

REFERENCES

1. 10CFR50; Appendix A, Criterion 1,2,13,19,64
2. Updated FSAR; Sections 9.13.4 and 11.3.5 ,
3. Technical Specifications 3/4.3.3. and 3/4.7.7 and bases.
4. Environmental Technical Specifications N/A
5. Source Document - Design Concept DCP 711, Rev. O, Dated 4/21/86.
6. Standard Review Plan, Section 9.4.5 Rev. 2 and 11.5 Rev. 3.
7. Drawings N/A
8. NRC Reg. Guides, Number 1.75 Rev. 2, 1.89 Rev. 1, 1.100 Rev. 1
9. Engineering Memorandum 72,345
Prepared by i Nlf f-d *hf K\\ J. Frederick Date Checked by '

7[Fl

/ S. A. Nass Date Approved by h [8M [ /8d Date

/ E. F. K Wtz, Jr.

Review by OSC at Meeting No. dV-@C-ell-86 Date d 29!D* W 9$

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OSC Action: Accept Reject Returned with Comments OSC Chairman

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