ML20058H869

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Proposed Tech Specs Revising Tech 3.3-6,Table 4.3.3 & Section B 3/4.3.3.1 Re Radiation Monitoring Instrumentation
ML20058H869
Person / Time
Site: Beaver Valley
Issue date: 07/30/1982
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20058H834 List:
References
NUDOCS 8208090095
Download: ML20058H869 (9)
v • d • e


Text

.

ATTACINElff A

1. Remove pages 3/4 3-34, 3/4 3-35, 3/4 3-36, B 3/4 3-2.
2. Insert pages 3/4 3-34, 3/4 3-34a, 3/4 3-35, 3/4 3-36, 3/4 3-36a, B 3/4 3-2.

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l 8208090095 820730 PDR ADOCK 05000334 P PDR

TABI.E 3.3-6 RADIATION MONITORING INSTRUMENTATION ,

w MINIMUM p CilANNELS APPLICABLE MEASUREMENT

,1 i NSTKilMENT OPERABLE MODES SETPOINT# RANCE ACTION

o

@ 1. AREA MONITORS r

a. Fuel Storage Pool Area 1 *

(15 mR/hr 10

~I

- 100mR/hr 19 (RM-207)

b. Containment a

" i. Purge & Exhaust 6 Isolation (RMVS 1 6 $1.6 x 10 3cpm 10 - 10 cpm 22 104 A & B)

N 7

@w 11. Area (RM-RM-2 L9 A & B) 2 1, 2, 3, & 4 $30 R/hr 1 - 10 R/hr 36 81:

Om gi 2. PROCESS MONITORS gs

$ a. Containment I!

1. Caseous Activity Purge & Exhaust 2 6 Isolation (RM-215B) 1 6 $7.3 x 10 cpm 10 - 10 cpm 22 RCS leakage Detection 1 1, 2, 3, & 4 N/A 10 - 10 cpm 20 (RM 215B)
11. Pa rt iculate Activi ty Purge & Exhaust 5 6 Isolation (RM 215A) 1 6 $2.5 x 10 cpm 10.- 10 cpm 6

22 RCS leakage Detection i 1, 2, 3, & 4 N/A 10 - 10 cpm 20 (RM 215A) 6

b. Fuel Storage Building 1 ** $4.0 x 100 cpm 10 - 10 cpm 21 Cross Activity (RMVS -

103 A 6 B)

  • LJith fuel in the storage pool or building
  • LJith irradiated fuel in the storage pool
  1. Aleve background

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION as MINIMUM 9 CHANNELS APPLICABLE MEASUREMENT w

INSTRUMENT OPERABLE MODES SETPOINT# RANGE ACTION E PROCESS MONITORS (Continued)

Q c. Noble Gas Effluent Monitors

1. Supplementary Leak 2 -2 i 1, 2, 3, & 4 3L3.5 X 10 cpm 10 - 10 uCi/cc* 36 5

H Collection and Release System (RM-VS-110 Ch. 7 &

Ch. 9) ***

11. Auxiliary Building 1 1, 2, 3, & 4 4 2.75 X 102cpm 10

-2

- 10 uCi/cc* 36

,, Ventilation System 2 (RM-VS-109 Ch. 7 & Ch. 9) ***

EN #'

$ 111. Process Vent System 4 -2 5 i 1, 2, 3, & 4 1 1.8 X 10 cpm 10 - 10 uci/cc** 36

" I' (RM-CW-109 Ch. 7 & Ch. 9) ***

E$

2." iv. Atmospheric Steam Dump 1/S.G 1, 2, 3, & 4 I 15.0 X 10 cpm 10

-1 ' 3

- 10 uC1/cc 36 7

Valve and Code Safety Relief Valve Discharge '

(RM-MS-100 A, B, C)

v. Auxiliary Feedwater Pump 1 1, 2, 3, & 4 2 -1 3 d6.5 X 10 cpm 10 - 10 uCi/cc 36 Turbine Exhaust (RM-MS-101)
  • Nominal range for Ch. 7 and Ch. 9. Alarm set on Ch. 7
    • Nominal range for Ch. 7 and Ch. 9.i Alarm set on Ch. 9
      • Other SPINC-4 channels not applicable to this specification
  1. Above background

. . T TABLE 3.3-6 (Continued)

TABLE NOTATION ACTICN 19 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require-ment, perform area surveys otthe' monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. i '

ACTION 20 -

With the number of channels OPERABLE less than required by the Minimum Channe/s OPERABLE require- 5 ment, comply with the ACTION requirements of Specification 3.4.6.1. ,

ACTION 21 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require-me n t , comply with the applicable ACTION requirements of Specifications 3.9.12 and 3.9.13.

ACTION 22 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE require- '/t ment, comply with the ACTION requirements of Specification 3.9.9. f .

I ACTION 36 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE require- ,

ment, either restore the inoperable Channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

1) Initiate the preplanned alternate method of monitoring the appropriate par'ameter(s), and \

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2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days following the event j outlining the action taken, the cause of the l inoperability and the plans and schedule for g restoring the system to OPERABLE status.

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s i l BEAVER VALLEY - UNIT 1 3/4 3-35 '

l l PROPOSED WORDING 4, .

s 1

3

l TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIRDIENTS *

, # CHANNEL MODES IN Wi!ICH p CilANNEL - CHANNEL FUNCTIONAL SURVEILLANCE y INSTRUMENT CllECK CALIBRATION TEST REQUIRED w

y 1. AREA }X)NITORS 5

y a. Fuel Storage Pool Area S R H *

, (RM 207) ~* .

y:

3 b. Containment a

.j l. Purte & Exhaust

  1. , j, Isola tion S R H 6 (RMVS 104 A & B) -

m

~

v

  • g _ 11. Area (RM-RM-219 A & B) S R M 1.2.3,64- I f

IM ~ l f

o. ta g 2. PROCESS' MONITORS .;

o 09 a. Containment

i. Caseous Activity Purge & Exhaust S R H 6 Isola tion (RM 215B)

RCS Ixakage Detection (RM 215B) S R M 1, 2, 3, & 4

11. Particulate Activity Purge & Exhaust Isolation (RM 215A) S R M 6 RCS leakage Detection (RM 215A) S R H 1, 2, 3, & 4
b. Fuel Storage Building S R H **

Gross Activity (RMVS 103 A & B)

  • With fuel in the storage pool or building.
    • With irradiated fuel in the storage pool

TABLE 4.3-3 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ex:

<j 33 CilANNEL MODES IN WHICH CilANNEL CllANNEL FUNCTIONAL SURVEILLANCE IS

.y INSTRUMENT CllECK CALIBRATION TEST REQUIRED E

R

, PROCESS HONITORS (Continued) c

$ c. Noble Gas Effluent Monitors a

~ 1. Supplementary Leak Collection and Release S R M 1, 2, 3, & 4 System (RM-VS-110 Ch. 7

y & Ch. 9)

Ou 8 1:

ga 11. Auxiliary Building g J, Ventilation System S R M 1, 2, 3, & 4 op (RM-VS-109.Ch. 7 & Ch. 9)

D e

111. Process Vent System (RM-GW-109 Ch. 7 & Ch. 9) S R M 1, 2, 3, & 4 iv. Atmospheric Steam Dump Valve and Code Safety S R M 1, 2, 3, & 4 Relief Valve Discharge (RM-MS-100 A, B, C)

v. Auxiliary Feedwater Pump S R M 1, 2, 3, & 4 Turbine Exhaust (RM-MS-101)

INSTRLMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:

L) the radiation levels are continually measured in the areas served by the individual channels; 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and 3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of NUREG-0737, " Clarification of TMI Action Plan Requirements," October, ,

1980.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified min-imum complement of equipment ensures that the teasurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradia-ting each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring F (Z) or FNH, a full incore flux map is used. Quarter-core flux maps, as d0 fined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the Quadrant Power Tilt Ratio when one Power Range Channel is inoperable.

3/4.3.3.3 SEISMIC INSTRUMENTATION The GPERABILITY of the seismic instrumentation ensures that suf ficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility and is consistent with the recom-mendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes."

l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION l

The OPERABILITY of the meteorological instrumentation ensures that suf ficient meteorological data is available for estimating potential radi-ation doses to the public as a result of routine or accidental release of l radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs."

BEAVER VALLEY - UNIT L B 3/4 3-2 Proposed Wording L

ATTACHMENT B This safety evaluation applies to the proposed revisions to the Beaver Valley Power Station, Unit No.1 Technical Specifications, Appendix A. Section 3.3.3.1, Radiation Monitoring. These changes are required as a result of the implementation of NUREG-0737 Items II.F.1.1, II.F.1.2, and II.F.1.3. The applicable plant modifications were incor-porated by DCP 303, Containment and Ef fluent Radiation Monitors. The required revisions to the Technical Specification include:

a) Table 3.3-6, Radiation Monitoring Instrumentation was expanded to include the high range containment area radiation monitors (RM-RM-219A,B) and the noble gas ef fluent monitors (RM-VS-110; RM-VS-109; RM-GW-109; RM-MS-100A,B, and C; RM-MS-101). Action statement 36 was included and is applicable to the above monitors.

b) Table 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements, was expanded to include applicable surveillance requirements for the monitors listed in a).

c) The BASES for Section 3.3.3.1 were revised to reflect the additional capability to monitor selected plant areas and process systems afforded by the new monitors and to indicate that this capability is responsive to the recommendations of NUREG-0737.

Ihe above changes are stated as required by NUREG-0737 and the specific requirements are consistent with the Westinghouse Standard Technical Specifications; NUREG-0452, Revision 4 The applicable portions of this document were forwarded to us for use in preparation of this proposed change by NRC letters dated October 7, 1981, and November 6, 1981. The October 7,1981, letter included Section 3.3.3.1 for incorporation into our Technical Specifications, our present Technical Specifications have this section and the wording is identical, therefore, this section was not included in this proposed change.

The FSAR was reviewed and it was determined that FSAR update will be required to incorporate the DCP 303 design modifications. FSAR Sections 9.13 Ventilation Systems, 11.3.3 Process and Effluent Radiological Monitoring System,11.3.4 Area Radiation Monitoring System, Table 11.3-2, Table 11. 3-3, Figure 11.2-2 and Figure 5.1.1 will b2 revised in 1983 to include the applicable monitors. The accident analyses in Section 14 were reviewed as to possible impact from these proposed Technical Specification changes. The applicable sections are 14.2.1 Fuel Handling Accident, 14.2.3 Accidental Release of Waste Cases,14.2.4 Steam Generator Table Rupture and 14. 3 Loss of Coolant Accident. Neither the probability of these occurrences nor the consequences of these postulated accidents will be increased due to the addition of the new monitors into the Technical Specifications.

Attachment B Page 2 Rather, the new monitors will provide additional information to the operators concerning concentrations and dispersions of radioactivity that wocid result from these postulated events and better enable the operator to maintain the resultant offsite dosages to within the prescribed limits of 10 CFR 100.

The addition of the high range containment area radiation monitors and the noble gas radiation monitors into Table 3.3-6, Radiation Monitoring Instrumentation, will not create the possibility for an accident or malfunction of safety related equipment of different types than previously evaluated in the FSAR. The new monitors provide additional information about existing plant areas and equipment and appropriate safeguards were implemented which separated and isolated or protected existing safety related equipment to prevent any adverse interactions of the new and existing equipment which could create the possibility of a new type of malfunction. The additional information available to the operator f rom the radiation monitors through the attendant control terminals, readout displays and microprocessors in the control room will better enable the operator to be aware of changing plant conditions and respond in an appropriate manner. The alarm setpoints were selected such that they correspond to site area emergency or general emergency criteria, thereby preventing spurious alarms which might cause the operator to react erroneously or creating the possibility of a new type of accident occurring. Therefore, this proposed Technical Specification change does not represent an unreviewed safety question.

The incorporation of the additional monitors into Table 3.3-6 and Table 4.3-3 will not affect the margin of safety as defined in the bases to Appendix A, B 3/4 3.3.1, Radiation Monitoring Instrumentation and Appendix B Environmental Technical Specifications, Section 2.4.3 and Section 2.4.4. The new monitors do not diminish the capability of the existing radiation monitoring systems to continuously monitor radiation levels and initiate apprcpriate alarms or automatic actions when the applicable radiaticn level trip setpoints are exceeded. The proposed revisions to the bases to reflect the new capability to monitor additional selected plant paramters and assess these variables after an accident clearly indicates that the margin of safety has been improved by the incorporation of the new monitors into the Technical Specifications.

The OSC and the ORC have reviewed this proposed change and based on the above safety evaluation, it is concluded there is reasonable assurance that the public health and safety will not be endangered by operation in the proposed manner.

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