Text

Amend 51 to License NPF-57,revising Tech Specs to Conform to Guidance in GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping
	ML20097B277
Person / Time
Site:	Hope Creek
Issue date:	06/01/1992
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20097B279	List: ML20097B277; ML20097B282;
References
	GL-88-01, GL-88-1, NUDOCS 9206040291
	Download: ML20097B277 (14)
	v • d • e

.

[rnog*'o UNITED STATES 8'

?,

NUCLEAR REGULATORY COMMISSION h

WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY P0CKET NL 50-354

@PE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-57 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Public Service Electric &

Gas Company (PSE&G) dated July 25, 1991, as supplemented May 11, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; l

D.

The. issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this an,endment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

9206040291 20601 PDR ADOCK 05000354 P

PDR

i

. (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h Y. N J

Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 1, 1992

o.

ATTACHMENT TO LICENSE AMEN 0 MENT N0. 51 FACILITY OPERATING l.lCENSE NO. NPF-5Z DOCKET N0, 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment number anJ contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness

Remove Insert 3/4 0-3 3/4 0-3 3/4 4-9 3/4 4-9*

3/4 4 10 3/4 4-10 3/4 4-10a 3/4 4-10b 3/4 4-11 3/4 4-11 3/4 4-12 3/4 4-12 B 3/4 0-5 8 3/4 0-5*

B 3/4 0-6 B 3/4 0-6 B 3/4 4-3 B 3/4 4-3 8 3/4 4-4 B 3/4 4-4

= i i.

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

Pressure Vessel; Code and applicable ~ Addenda shall be applicable as follows in_these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly

_At least once per 7 days Monthly At least_once per 31 days Quarterly or every 3 months At least once per_92 days Semiannually or every 6 months At least once per 184-days Every 9 months At least once per 276' days Yearly or annually At least once per 366 days c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing-activities, d.

Performance of the above inservice inspection and_ testing activities shall be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME~ Boiler and Pressure Vessel Code shall be con-

'strued to supersede the requirements of_-any Technical Specification.

f.

_The Inservice Inspection Program for-piping identified in NRC Generic Letter 88-01 shall conform to the staff positions on schedule, methods, and personnel, and sample expansion included in that generic letter, or as-otherwise approved by the NRC.

8 HOPE CREEK 3/4 0-3 Amendment No. 51

.~.-. - -

=

1 4

REACTOR C00LANT SYSTEM SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION LIMITING CONDITION FOR OPERATION 3.4.2.2 The relief valve function and the low-low set fuaction of the following reactor coolant system safety / relief valves shall be OPERanLE with tha following settings:

Low-Low Set Function Setooint* (psfo) 22%

Valve No.

Open Close F013H 1017 905 F013P 1047 935 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the relief valve function and/or the low-low set function of-one of a.

the above required reactor coolant system safety / relief valves inoperable, restore the inoperable relief valve function and low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within

' the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With the relief valve function and/or the low-low set function of both of the above required reactor coolant system safety / relief valves

-inoperable, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2.2.1. The relief valve function and the low-low set function pressure actuation _ instrumentation shall be demonstrated OPERABLE by performance of at CHANiiEL FUNCTIONAL TEST at least once per 31 days.

a.

b.

CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of the entire system (excluding actual valve actuation) at least once-per 18 months.

"The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

HOPE CREEK 3/4 4-9

f REACTOR COOLANT SYSTEM 3/4. 4.-3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

The drywell floor and equipment drain sump monitoring system, a.

b.

The drywell atmosphere gaseous radioactivity monitoring system, c.

All three of_the following:

1.

The drywell air cooler condensate flow rate monitoring system, 2.

The drywell pressure monitoring system, and 3.

The drywell temperature monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With the drywell floor and equipment drain sump monitoring system a.

inoperable:

1.

operation may continue for 30 days provided that all monitoring systems in 3.4.3.1.b and 3.4.3.1.c are OPERABLE, and provided that preplanned manual calculation to quantify leak rate is performed at least once per four hours, or 2.

restore the system to CPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With the drywell atmosphere gaseous radioactivity monitoring system inoperable, operation may continue for 30 days provided that the monitoring systems required by 3.4.3.1.a and 3.4.3.1.c are OPERABLE, and provided that grab samples of the drywell atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With one monitoring system in 3.4.3.1.c inoperable, exert best efforts to restore the system to OPERABLE status within 30 days and if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause for the malfunction and plans for restoring the system to OPERABLE status.

With two less than-the number-of monitoring systems required by 3.4.3.1.c OPERABLE, operation may continue for up to 30 days, provided that the drywell floor and equipment drain sump monitoring system in 3.4.3.1.a and the drywell atmosphere gaseous radioactivity monitoring system in 3.4.3.1.b are OPERABLE.

__d.

Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 nours.

HOPE CREEK 3/4 4-10 Amendment No. 51

i REACTOR C60NT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection' systems shall be demonstrated OPERABLE by:

Drywell atmosphere gaseous radioactivity monitoring system performance a.

of a CHANNEL CHECX at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months, b.

The drywell pressure shall be monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and the drywell temperature shall be monitored at least onca per 24

hours, c.

Drywell floor and equipment drain sump monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months, d.

Drywell air coolers condensate flow rate monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

HOPE CREEK 3/4 4-10a Amendment No. 51

4J A

4 a4 s 3

f.

REACTOR COOLANT SYSTEM k

TH15 PAGE INTENTIONALLY BLANK HOPE CREEK 3/4 4-10b Amendment No. 51

i REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE.

c.

25 gpm IDENTIFIED LEAKAGE averaged over any 24-hour period.

d.

0.5 gpm leakage per nominal inch of valve size up to a maximum of 5 gpm from any reactor coolant system pressure isolation valve specified in 7 able 3.4.3.2-1, at rated pressure.

2 gpm increase in UNIDENTIFIED LEAKAGE within any period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months e.

or less.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use o' si least one other closed manual or deactivated automatic or check

valv i.

or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in L M SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-2 inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alarm setpoint at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the fcllowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e.

With any increase in UNIDENTIFIED LEAKAGE exceeding the limit in e above, implement preplanned leak location and isolation actions and either verify that the source of the leakage is not service-sensitive type 304 or 316 stainless steel or reduce the leakage rate-of-change to less than the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following-24 hours.

Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.

HOPE CREEK 3/4 4-11 Amendment No. 51

f 1

REACTORCOOLANTSYSTg SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

Monitoring the drywell atmospheric gaseous radioactivity at least a.

once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (not a means of quantifying leakage),

b.

Monitoring the drywell floor and equipment drain sump flow rate at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and c.

Monitoring the drywell air coolers condensate flow rata at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and l

d.

Monitoring the drywell pressure at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (not a l

means of quantifying leakage), and Monitoring the reactor vessel head flange leak detection system at e.

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (not a means of quantifying leakage), and f.

Monitoring the drywell temperature at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (not a means of quantifying leakage).

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months,** and c

b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2 by performance of a:

a.

CHANNEL FUNCTIONAL.TES1 at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.

- P.I.V. leak test extension to the first refueling outage is permissible for each RCS P.I.V. listed in Ta_;e 3.4.3.2-1, that is identified in Public Ser-

,~

vice Electric & Gas-Company's letter to the hRC (letter No. NLR-N87047),

dated April 3, 1987, s needing a plant outage to test.

For this one time test interval, the requirements of Section 4.0.2 are not applicable.

HOPE CREEK 3/4 4-12 Amendment No. 51 1

e

^

3/4.0 APPLICABILITY BASES (Con't) be construed as implying that systems or compa its are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Require-ments.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION require-ments apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not-negate the fact that the failure to have performed the surveillance within the allowed surveil-lance interval, defined by the provisions of Specification 4.0.2, was a viola-tion of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action, Further, the failure to perform a surveil-lance within the provisions of Specification 4.0.2 is a violation of a Techni-cal Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel,'the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the-time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define thu remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable surveil-lances must De met before entry into an OPERATIONAL CONDITION or other HOPE CREEK 8 3/4 0-5 Amendment No. 19 SEP 2 81989_

e 3/4.0 APPLICABILITY BASES (Con't) condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITIONS of operation.

Specification 4.0.5 establishes the requirement that inservice inspection of A59 Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a claiificat on of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarifica-tion is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequen-cies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months befure being declared inoperable.

This specification includes inservice inspection requirements that conform to the guidance of Generic Letter 88-01, "NRC Position on IGSCC in BWR Austinitic Stainless Steel Piping."

HOPE CREEK B 3/4 0-6 Amendment No. 51

REACTOR COOLANT SYSTEM BASES 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage fron, the reactor coolant pressure boundary.

These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems", May-1973 and Generic Letter 88-01, "NRC Position on IGSCC in BWR Austinitic-Stainless Steel Piping."

Proceduralized, manual quantitative monitoring and calculation of leakage rates,-found by the NRC staff, in GL 88-01, Supp. 1, to be an acceptable alternative during repair periods of up to 30 days, should be demonstrated to have accuracy comparable to the installed drywell floor and equipment drain sump monitoring system.

3/4.4.3.2 OPERATIONAL LEAKAGE The. allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes.

The normally expected background leakage due to equipment design and the detection capability of the. instrumentation for determining system leakage was also con-i sidered.

The evidence-obtained from experiments suggests that for leakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly.

However, in all cases, if the leakage rates exceed the values specified or the-leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.

The= Surveillance Requirements for RCS' pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of. gross valve failure and consequent intersystem LOCA.

Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the. allowed limit.

The limit placed upon the rate of increase in UNIDENTIFIED LEAKAGE meets the guidance of Generic Letter 88-01, "NRC Position on IGSCC in BWR Austinitic Stainless 15 teel Piping."

3/4.4.4 CHEMISTRY The water chemistry-limits of the reactor. coolant system are established

-to prevent damage to the reactor materials in contact with-the coolant.

Chloride

limits are specified to prevent stress corrosion cracking of the stainless steel.

The effect of chloride is not as great when tne oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is pennitted during POWER OPERATION.

During shutdown and refueling operations, the temperature necessary for. stress corrosion to occur is not present se a 0.5 ppm concentration of-l chlorides is not considered harmful during these periods.

HOPE CREEK B 3/4 4-3 Amendment No. 51

REACTOR COOLANT SYSTEM f

BASES CHEMISTRY (Continued)

Conductivity measurements are required on a continueus basis since changes in this parameter are an indication of abnormal conditions.

When the conductivity is within limits, the pH, chlorides and other impurities affecting conduc+ivity must also be within their acceptable limits. With the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective actinn.

3/4.4.5 SPECIFIC ACTIVITY The limitations on tha specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100.

The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.

These values are conservative in that specific site parameter;,, such as site boundary location and meteorological conditions, were not considered in this evaluation.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram 00SE EQUIVALENT I-131, but less than or equal to 4.0 micro-curies per gram DOSE EQUIVALENT I-131, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.

Monitoring the iodine activity in the primary coolant and taking responsible actions to maintain it at a reasonably low level will aid in ensuring the accumulated time of plant operation with high iodine activity will not excced 800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months in a consecutive 12-month period.

The results of all primary coolant specific activity analyses which exceed the limits of Specification 3.4.5 will be documented pursuant to Specification 6.9.1.5.

Information obtained on iodine spiking will be used to assess the 4

parameters associated with spiking phenomena.

A reduction in frequency of isotopic analysis following power changes may be permissible if justified by the data obtained.

Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment, lhe surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolant will be detected in sufficient time to take corrective action.

HOPE CREEK B 3/4 4-4 Amendment No. 51

_ _ - _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

ML20097B277

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