Text

Proposed Tech Specs in Hydrologic & Geotechnical Engineering & Meteorology & Effluent Treatment Sys Branch Areas of Review
	ML20092G884
Person / Time
Site:	Grand Gulf
Issue date:	06/20/1984
From:	; MISSISSIPPI POWER & LIGHT CO.
To:	;
Shared Package
ML20092G876	List: AECM-84-0315, Application for Amend to License NPF-13,changing Tech Specs in Hydrologic & Geotechnical Engineering & Meteorology & Effluent Treatment Sys Branch Areas of Review; ML20092G884;
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ATTACHMENT 1 PROPOSED CHANGES TO THE GRAND GULF NUCLEAR STATION TECHNICAL SPECIFICATIONS NRC TECHNICAL REVIEW BRANCH: HYDROLOGIC AND GEOTECHNICAL ENGINEERING O

g6250274840620 ADOCK 05000416 p

PDR TS60mm2

AttcchmInt 1 / Hydrologic cnd Geotschnical Engineering AECM-84/0315 (6/20/84)

Page 2 Listing of Item Numbers by

- Technical Specification Eroblem Sheet (TSPS) Number TSPS No.

Item Nos.8 133 1.D.01 i

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Item number format:

1.A.02 Item number within category Category designator Attachment number l

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TYPOGRAPHICAL ERRORS, EDITORIAL CHANGES, AND CLARIFICATIONS No t'echnical specification changes in this category are included with this attachment.

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TECHNICAL SPECIFICATION /AS-BUILT PLANT CONSISTENCY No technical specification changes in this category are included with

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this attachment.

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ENHANCEMENTS THAT ARE CONSISTENT WITH THE SAFETY ANALYSES i

No t'echnical specification changes in this category are included with this attachment.

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REGULATORY REQUIREMENTS / REQUESTS / RECOMMENDATIONS The following change is proposed to ren' der the technical specification

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consistent with recent changes in NRC policy and the Code of Federal Regulations, as well as to implement changes or enhancements recenQ l

requested or recommended by NRC reviewers.

i This proposed change is required to render the technical specification l

consistent with recent NRC guidance, and it has been concluded based on a l

review of this item that the proposed change does not:

Involve a significant increase in the probability or consequences of o

an accident previously evaluated; or Create the possibility of a new or different kind of accident from any o

accident previously evaluated; or Involve a signiftcant reduction in a margin of safety.

o Therefore, the proposed change does not involve a significant hazards consideration.

A description of this change including justification for the change is provided below:

(TSPS 133) Embankment Stability, Technical Specification 3.7.10 and 1.

Administrative Controls, Procedures and Programs 6.8.1 The existing Techncial Specification 3/4.7.10 was proposed by MP&L in f

AECM-83/0370 dated June 29, 1983, in order to implement a requirement in Supplement 1 to the GGNS Safety Evaluation Report (SER). The SER requirement involves implementation of the provisions of Regulatory Guide 1.127, " Inspection of Water Control Features Associated with Nuclear Power Plants" for the slopes of the access rosd and drainage basin at Culvert No. 1.

Adminsitrative changes to Specification i

3/4.7.10 were requested by MP&L on September 9, 1983 (AECM-83/0565).

25, 1984 These proposed changes were subsequently withdrawn on May (AECM-84/0303).

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These required inspections do not represent limiting conditions for operation as passive flood control measures, which are consistent with l

Regulatory Guide 1.102, have been provided at GGNS to protect safety related equipment from the effects of flooding. The proposed change deletes Technical Specification 3.7.10 and adds a new Administrative r

Control Specification, 6.8.1.j.

The inspections dealt with in l

Specification 3.7.10 will be included in the plant administrative procedures under this new specification. This change does not i

adversely affect plant safety since the plant administrative proce-dures will continue to ensure that detailed inspections of the embank-l ment structure upstream of Culvert No. I are performed, using the guidance of Regulatory Guide 1.127. This proposed change is in response to an NRC proof and review comment and constitutes an enhance-(Page 3/4 7-46, 6-14) ment to the present technical specifications.

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PROPOSED TECHNICAL SPECIFICATION CHANGES (AFFECTED PAGES ARE PROVIDED IN THE ORDER OF ASCENDING PAGE NUMBERS.)

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10 EMBANKMENT STABILITY LIMITING DITION FOR OPERATION r

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3.7.10 The downs eam access road slope at Culvert No. I a the drainage tiasin slopes shall ain stable.

i APPLICABILITY:

At all t s.

i ACTION:

If Culvert No. I ha blockage exceeding

% of its cross-sectional l

area, the Culvert shall be cle ed and the slo embankments verified to be stabl e'.

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-SURVEILLANCE REQUIREMENTS s

x 4.7.10 The downstream acce road slope at Culve No. I and the drainage basin slopes shall be con rmed to be stable by.

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s.

At least once p year, performing a visual inspect

n of*the' embankments and Culvert N. 1.,

b.

At least ce per' five years, performing a five year surv to confirm no signif nt degradation to the base-line data.

c.

Fo owing the occurrence of earthquakes, hurricanes, tornados, o intense cal rainfalls, a visual inspection of the embankments and Culver No. I will be made.

If this special inspection reveals evidence of change, a survey will be performed to confirm no significant degradation to the 3

l base-line data.

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h GRAND GULF-UNIT 1 3/4 7-46 Amendment No. 9 l

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4 ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.'

The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Senior Vice President - Nuclear within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

i.

Quality Assurance Program for effluent and environmental monitoring, using the guidance %n Regulatory Guide 4.15, February 1979.

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Embankment Stabili Ver:Ficattm R ogram W) l J'

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed as required by 6.5, above, prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

l 6.8.3 The following programs shall be established, implemented, and maintained:

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a.

Primary Coolant Sources Outside Containment l

A program to reduce leakage from those portions of systems outside l

containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.

The systems include the:

1.

RCIC system outside containment containing steam or water, except the drain line to the main condenser.

2.

RHR system outside containment containing steam or water, except the line to the LRW system and headers that are isolated by manual valves.

3.

HPCS system.

4.

LPCS system.

5.

Hydrogen analyzers of the combustible gas control system.

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r-l ATTACHMENT 2 PROPOSED CHANGES TO THE GRAND GULF NUCLEAR STATION TECHNICAL SPECIFICATIONS NRC TECHNICAL REVIEW BRANCH: METEOROLOGY AND EFFLUENT TREATMENT I

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Page 2 Listing of Item Numbers by Technical Specification Problem Sheet (TSPS) Number Item Nos.*

TSPS No.

018 2.A.04 045 2.A.05, 2.A.01 062 2.A.08 087 2.D.01 l

122 2.D.02, 2.A.03 138 2.B.01 185 2.C.01, 2.A.02 193 2.C.02 262 2.B.02 311 2.C.03 348 2.A.06 349 2.B.03 361 2.A.07 l

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Item number format:

1. A. 02 I

l Item number within category Category designator Attachment number TS65rg2

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Page 3 A.

TYPOGRAPHICAL ERRORS, EDITORIAL CHANGES, AND CLARIFICATIONS These proposed changes correct obvious typographical errors, implement editorial changes such as correction of spelling errors, punctuation errors, and grammatical errors or provide clarification of the basic meaning or intent of the subject technical specifications.

MP&L has determined that the proposed changes do not;

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Involve a significant increase in the probability or consequences of o

an accident previously evaluated; or Create the possibility of a new or different kind of accident from any o

accident previously evaluated; or Involve a significant reduction in a margin of safety.

o Therefore, the proposed changes do not involve a significant hazards consideration.

A description of these changes including necessary justification for the l

changes is provided below:

TYPOGRAPHICAL ERRORS Typographical errors are being corrected by this' submittal as listed below. Correction of these typographical errors is purely an administra-tive change.

(See attached revised technical specification pages for exact changes proposed.)

TSPS No.

TS Page No.

B 3/4 3-6 1.

045 3/4 11-17 2.

185 3/4 3-95 3.

122 I

CLARIFICATIONS l

I Clarifications to the technical specifications to improve understanding and readability are discussed below:

l 4.

(TSPS 018), Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation, Technical Specification 3/4.3.7.11 and 3/4.3.7.12 The proposed change clarifies that an explanation in the Semiannual Radioactive Effluent Release Report is needed only if attempts to restore the required channels to OPERABLE status in a timely manner are unsuccessful. Also, the "Offsite Dose Calculation Manual" has been capitalized in technical specification 3.3.7.11 to be consistent with the standard format of the technical specifications. The pro-posed changes represent clarifications which do not adversely impact e

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. plant safe'ty.and which do not change the intent of the specifications.

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(Pages 3/4 3-82 and 3/4 3-87)

(TSPS 045), Radioactive Gaseous Effluent Monitoring Instruinentation, l

5.

Technical Specification 3/4.3.7.12 I

The proposed change clarifies two aspects of Technical Specification 3.3.7.12:

The current wording implies that the OFFSITE DOSE CALCULATION MANUAL (ODCM) prescribes the alarm / trip setpoints for all the

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a.

i instruments in Table 3.3.7.12-1 and bases. The ODCM does not l

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apply to the Explosive gas monitor, the Offgas Pretreatment i

Monitor or the Offgas Post-Treatment Monitor, as these instruments do not monitor effluent discharge points.

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A footnote has been added to provide the limits for the Explosive b.

Gas Monitor and the Offgas Pretreatment Monitor are provided in j

l Specifications 3.11.2.6 and 3.11.2.7, respectively.

'The is a purely administrative. change to clarify and achieve consistency in the Technical Specifications and, as such, will beve no l

adverse impact on plant safety.

(Pages 3/4 3-87 and B 3/4 3-6) l t

(TSPS 348), Meteorological Monitoring Instrumentation. Technical l

6.

Specification 3/4.3.7.3 This proposed change clarifies that the requirement for a special i

report is applicable only when there are less than the minimum number i

of channels required to be OPERABLE by Technical Specification Table

_3.3.7.3-1.

The current wording of this specification could be I

misinterpreted to require a special report.when any of the presently

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installed instrumentation channels are inoperable. This change is 1

purely administrative in that it is a clarification to reflect the t

design intent and is consistent with the recommendations of Regulatory (Page Guide 1.23 "Onsite Meteorological Programs," February,1972.

3/4 3-63)

(TSPS 361), Radioactive Liquid Effluent Monitoring Instrumentation and 7.

3.3.7.11-1 i

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Surveillance Requirements. Technical Specification Tables and 4.3.7.11-1 The proposed change adds the phrases " alarm and" to Item 1 on Page 3/4 l

3-83 and "or Circulating Water Blowdown" to Item 2b on Pages 3/4 3-83 l

and 3/4 3-85.

The addition of " alarm and" clarifies that an alarm l

The i

function exists as well as an automatic termination of release.

I addition of "or Circulating Water Blowdown" provides an alternate flow i

I measurement that is more conservative than the discharge canal flow measurement, since the circulating water blowdown is only a part of l

the total canal discharge. This alternate method of measurement is acceptable at any time the circulating water system is in service and is consistent with the as-built plant condition. These changes do not i

adversely impact plant safety because they are clarifications that are l

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tions.

(Pages 3/4 3-83 and 3/4 3-85) 8.

(TSPS 062), Standby Gas and Control Room Emergency Filtration Systems, Technical Specification Bases 3/4.6.6 and 3/4.7.2 Technical Specifications 4.6.6.3.a and 4.7.2.a require that each standby gas treatment and control room emergency filtration subsystem be demonstrated OPERABLE by initiating from the control room, at least once per 31 days, flow through the HEPA filters and charcoal adsorbers and verifying that each subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE. The intent of the requirement is to ensure that a continuous 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months operation of each subsystem is performed with the heaters OPERABLE to reduce the buildup of moisture in the adsorbers and HEPA filters. When these specifications are referenced to their bases, misinterpretation may occur as to whether a continuous or a cumulative 10-hour period of operation is required. This proposed change clarifies the intent of the requirement by inserting the word

" continuous" into the surveillance requirements in Technical Specifications 3/4.6.6 and 3/4.7.2 and by changing the word

" cumulative" to " continuous" in their associated Bases sections. This proposed change does not adversely impact plant safety as it repre-sents only a clarification of the intent of the surveillance require-ments.

(Page B 3/4 6-6 and B 3/4 7-1)

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TECHNICAL SPECIFICATION /AS-BUILT PLANT CONSISTENCY B.

The following changes are proposed to r' ender the technical specifications censistent with the as-built plant. In all such cases, the as-built plant is consistent with the safety analyses and the licensing basis.

In that these proposed changes are inherently consistent with the safety I

analyses and the licensing basis, it is concluded that the proposed changes do not:

i Involve a significant increase in the probability or consequences of o

an accident previously evaluated; or E

Create the possibility of a new or different kind of accident from any o

accident previously evaluated; or involve a significant reduction in a margin of safety.

o Therefore, the proposed changes do not involve a significant hazards consideration.

A description of these changes including justification for the changes is V

provided below:

(TSPS 138), Radioactive Gaseous Waste Sampling, Technical 1.

Specification Table 4.11.2.1.2-1 i

A revision to Technical Specification Table 4.11.2.1.2-1 concerning l

the Radioactive Caseous Waste Sampling and Analysis Program is proposed to restructure the table to more clearly reflect the The changes requirements for sampling radioactive gaseous waste.

These are consistent with the as-built plant design and operation.

proposed changes are as follows:

The gaseous release types will be revised to include two a.

functional categories:

A.) gaseous exhaust points requiring monitoring capability at all times, and B.) gaseous exhaust points requiring monitoring only when there is flow past these This portion of the change is purely administrative locations.

in that it affects only the organization of the table and does not alter its intent.

MP&L has determined that two additional grab sample points for l

b.

gaseous release, the radwaste building ventilation exhaust j

point and the fuel handling area ventilation exhaust point, fall within the scope of Technical Specification 3.11.2.1.

Provisions for periodic grab sampling at these gaseous exhaust r

points are included in Table 4.11.2.1.2-1 as items A.(1) and This change is an enhancement to safety in that it A.(2).

provides an additional monitoring requirement not included in the current specification.

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S' Note _b to Table 4.11.2.1.2-1 requires that grab sample analyses-c.

for principal gamma emitters and tritium be completed following startup from COLD SHUTDOWN or after a 15% or greater RATED THERMAL POWER chahge. The tritium analysis does not provide thformation directly related to power changes and is therefore not necessary.

Thet;efore, application of Note b is removed from the Sampling Frequency and Minimum Analysis Frequency column and added to the Type of Activity Analysis column where it applies only to Principal Camma Emitters. This change is a clarification which r s will not adversely impact plant safety because it does not reduce the amount of appropriate information being obtained from the required sample analyses.

The reference to Note f (currently in Section D) in Sect' ion A of d.

proposed Table 4.11.2.1.2-1 is a typographical error and will be f

eliminated since there is no Note f.

This is purely an administrative change that does not impact plant safety.

These proposed changes reflect the as-built plant design and are consistent with the requirements of 10 CFR 20.

(Page 3/4 11-9) s (TSPS 262), Standby Cas Treatment System (SGTS) Exhaust Monitoring 2.

System Technical Specification Tables 3.3.7.12-1, 4.3.7.12-1 and j

4.11.2.1.2-1

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This proposed change involves the SGTS Exhaust Monitoring System radiation monitors in Technical Specification Tables 3.3.7.12-1, 4.3.7.12-1 and 4.11.2.1.2-1 which contains the radioactive gaseous effluent monitoring instrumentation and the radioactive gaseous waste The SGTS Exhaust Monitoring System is sampling and analysis program.

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currently included in Technical Specification 3/4.3.7.5 for Accident c c Monitoring Instrumentation. The SGTS, however, may be operated for short periods of time for reasons other than the occurrence of an.

' accident (e.g., SGTS surveillance testing, secondary containment Since the(

integrity demonstrations, inadvertent initiation signals).

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SGTS provides a gaseous effluent release path when in service, the inclusion of the SGTS Exhaust Monitoring System in the Gaseous

5 The r-Efflu'ent Instrumentation Technical Specification is appropriate.

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Minimum OPERABLE Channel requirements, Applicability Requirements, r

ACTION statements and Surveillance Requirements proposkd for Tables 3.3.7.12-1 and 4.3.7.12-1 are consistent with the design of the associated SGTS exhaust noble gas activity monitors and are sufficient to assure adequate gaseous effluent monitoring. The proposed addition of the SGTS exhaust to Table 4.11.2.1.2-1 provides inclusion of SGTS exhaust contributions in the dose rate calculations if the SGTS has The, proposed changes are enhancements to'shfety in that been run.

they provide requirements not currently contained in the technical specifications to monitor effluent releases via the SGTS.

(Pages 3/4 3-90, 3/4 3-91( 3/4 3-94, and 3/4 11-9) i j

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(TSPS 349), Radiation Monitoring Instrumentation ACTION Statement, Technical Specification Table 3.3.7.,1-1 i

The proposed change to Item b. of ACTION 75 will specify that SECONDARY CONTAINMENT INTEGRITY must be established with at least one i

standby gas treatment subsystem operating when two of the three required monitors in either the fuel handling area ventilation exhaust or the fuel handling area pool sweep exhaust are inoperable. As indicated by footnote (d) to Table 3.3.7.1-1, a high radiation trip signal by the affected ventilation monitoring channels would isolate the auxiliary building and fuel handling area ventilation systems.

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The proposed change to ACTION statement 75 is necessary to ensure that j

this function provided by the ventilation monitoring channel.is implemented. The proposed change is an enhancement to plant safety as it represents a revision for the purpose of consistency with the t

as-built plant design and function and it constitutes an additional requirement not contained in the current technical specification.

(Page 3/4 3-58) 1 J

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ENHANCEMENTS THAT ARE CONSISTENT WITH THE SAFETY ANALYSES The following proposed changes are enhancements which are consistent with the safety analyses and the licensing basis and which provide clarifica-

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tion, render areas consistent with the philosophy and intent of the technical specifications, or provide additional plant operational margin.

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I Since these proposed changes are included in the current licensing bases and are bounded by existing safety analyses, the proposed changes do not:

l Involve a significant increase in the probability or consequences of l

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an accident previously evaluated; or Create the possibility of a new or different kind of accident from any o

accident previously evaluated; or I

Involve a significant reduction in a margin of safety.

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Therefore, the proposed changes do not involve a significant hazards consideration.

i A description of these changes including justification for the changes is provided below:

O 1.

(TSPS 185), Radioactive Effluents, Main Condenser, Technical Specification 3/4.11.2.7 and Table 3.3.7.12-1 The following changes are proposed to Specification 3/4.11.2.7:

Specific isotopes are deleted from the Limiting Condition for I

a.

Operation (LCO), the associated ACTION statement, and Surveillance 4.11.2.7.2 to make the Specification applicable to all noble gases that are existent after a 30 minute decay period.

l This allows for the decay of the short-lived noble gas isotopes which are not considered significant in effluent release considerations. This change therefore has no adverse impact on safety.

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A footnote is added to the applicability of Specification l

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3/4.11.2.7, for OPERATIONAL CONDITIONS 2 and 3, to reflect i

applicability only during operation of the main condenser air An additional footnote is provided for Surveillance ej ector.

4.11.2.7.2 to indicate that the provisions of Technical l

Specification 4.0.4 do not apply. These c5:anges have no adverse impact on safety since they are clarifications which indicate that there is no need to monitor air ejector effluent if the air ejectors are not in service.

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Page 10 The ACTION statement for Technical Specification 3.11.2.7 and c.

ACTION 126 of Table 3.3.7.12-1 (Table Notation) are revised to delete reference to HOT STANDBY. This term is not defined as an OPERATIONAL CONDITION in Technical Specification Table 1.2.

Additionally, the present ACTION statement does not require that the reactor be placed in an OPERATIONAL CONDITION where the LCO does not apply. Replacing the requirement to be in -

" HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months " with a requirement to be in " HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months " is consistent with the requirements of Specification 3.0.3 and places the appropriate OPERATIONAL CONDITIONS in the ACTION statements, d.

Surveillance 4.11.2.7.2 is revised to indicate that samples should be taken of the offgas recombiner effluent. The sample point used at Grand Gulf is downstream of the offgas recombiner. This change is consistent with the LCO and Grand Gulf design.

Surveillance Requirement 4.11.2.7.2.b is revised to replace e.

Condenser Air Ejector Noble Gas Activity Monitor with Offgas Pretreatment Monitor. This is a terminology change proposed to achieve consistency within the technical specifications and is in I

agreement with Table 3.3.7.12-1.

In summary, the proposed changes are consistent with the requirements of 10 CFR 100 as described in Bases Section 3/4.11.2.7 and do not affect any safety requirements. These changes improve safety by either requiring more stringent action or by clarifying the specifications.

(Pages 3/4 3-91 and 3/4 11-17) 2.

(TSPS 193), Applicability Change for Explosive Gas Mixture.

Technical Specification 3/4.11.2.6 The proposed change to the applicability statement for Technical Specification 4.11.2.6 will indicate that the specification is applicable only during operation of the Main Condenser Off gas Treatment System (i.e., the hydrogen concentration in the system will not increase unless the system is in operation). The word

" maintaining" in Surveillance Requirement 4.11.2.6 is changed to

" monitoring." ".-intaining" has no clear meaning in this context and is changed to clarify the requirement. This proposed change is purely administrative in that it provides clarification and is consistent with the intent of the technical specification.

(Page 3/4 11-16)

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(TSPS 311), Qhemical Release Clarification, Bases 3/4.6.6 and Bases 3/4.7.2 ihe proposed change to the bases for the Standby Gas Treatment System and the Control Room Emergency Filtration System will provide supplemental information on the design and performance of these The additional information will describe the adequacy of systems.

system's surveillance requirements to ensure charcoal adsorbency is maintained in the event of a chemical release in an associated ventilation zone. The proposed change has no adverse affect on plant safety as it represents a purely administrative change for the purpose i

of expanding the descriptions contained in the bases and does not affect system design or performance.

(Pages B 3/4 6-6, B 3/4 7-1)

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Page 12 D.

REGULATORY REQUIREMENTS / REQUESTS / RECOMMENDATIONS

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t The following changes are proposed to render the technical specifications i

consistent with recent changes in NRC policy and the Code of Federal Regulations, as well as to implement changes or enhancements recently requested or recommended by NRC reviewers.

These proposed changes are required to render the technical specifications consistent with recent NRC guidance, and it has been concluded based on a review of each item that the proposed changes do not; o

Involve a significant increase in the probability or censequences of an accident previously evaluated; or Create the possibility of a new or different kind of accident from any o

accident previously evaluated; or Involve a significant reduction in a margin of safety.

o Therefore, the proposed changes do not involve a significant hazards consideration.

A description of these changes including justification for the changes is provided below:

1.

(TSPS 087), Radioactive Gaseous Waste Sample and Analysis Program, Technical Specification Table 4.11.2.1.2-1 The proposed change adds a sentence to Table Notations b and c to indicate the conditions for which the requirements do not apply.

l Analysis for gamma emitter's is unnecessary for conditions following startup from COLD SHUTDOWN and THERMAL POWER changes of greater than 15 percent within one hour if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

Reactor coolant isotopic analysis for DOSE EQUIVALENT 1-131 concentra-tion is required on at least a monthly basis by Specification 3/4.4.5.

The noble gas monitors specified in Section A of the proposed change to Table 4.11.2.1.2-1 are continuous sample monitors. Since the reactor coolant activity and noble gas effluent activity are being monitored and will detect increases in activity levels, the grab samples are not required until the activity level shows a significant The proposed changes reflect the Grand Gulf design and are increase.

consistent with the requirements of 10 CFR 20.

(Page 3/4 11-11) 3 i

TS65rg12

-g.

Attachmtnt 2 / Matsorolegy and Efflutnt Treatosnt AECM-84/0315 (6/20/84)

Page 13 (TSPS 122), flow Rate Monitors Channel Functional Test, Technical 2.

Specification Table 4.3.7.12-1 This revision adds footnote number 5 to Technical Specification Table 4.3.7.12-1, and makes this footnote applicable to the CRANNEL FUNCTIONAL TEST requirements for the flow rate monitors in the exhaust monitor systems for the radwaste building ventilation, containment ventilation effluent, turbine building ventilation, and fuel handling area ventilation. The footnote requires that the measured flow rates be compared to the expected design flow rates for the existing plant conditions for these systems. This proposed revision supersedes a previous submittal (Item 19 of MP&L letter AECM-83/0565 dated September 9, 1983 which was withdrawn by MP&L letter AECM-P4/0303 dated May 25, 1984) which proposed that the CHANNEL FUNCTI'JNAL TEST requirements be deleted for these monitors. This change is submitted in its current form in response to an NRC concern that the requirements be retained and is considered to be a safety enhancement in that it represents a more stringent surveillance requirement.

(Pages 3/4 3-92, 3/4 3-93, and 3/4 3-95)

TS65rg13

I Attech2:nt 2 / Matsoroicgy j

and Efflutnt Trestant AECM-84/0315 (6/20/84) r I

Page 14 I

~

e I

E.

PROPOSED TECHNICAL SPECIFICATION CHANGES i

(AFFECTED PAGES ARE PROVIDED IN THE i

ORDER OF ASCENDING PAGE NUMBERS.)

I

+

t l

t i

i l

t I

i

?

o

[

i i-j t

I t

I i

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+

?

I TS65rgl4 r_

t INSTRUMENTATION TABLE 3.3.7.1-1 (Continued) l RADIATION MONITORING INSTRUMENTATION 3

ACTION t

With the required monitor inoperable, obtain and analyze at ACTION 70 least one grab sample of the monitored parameter at least once per 24 hcurs.

i ACTION 71 With one of the required monitors inoperable, place the a.

inoperable channel in the downscale tripped condition within one hour.

b.

With both of the required monitors inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , t

ACTION 72-With the required monitor inoperable, perform area surveys of the monitored area with portable monitoring instrumentation at

~

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

j ACTION 73 With one of the required monitors in a trip system inoperable, a.

place the inoperable channel in the downscale tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days, or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and i

maintain operation of at least one control reem emergency

-i filtration system in the-isolatien mede cf c;:aration.--

b.

With both of the required monitors in a trip system inoperable, i

initiate and maintain operation of at least one control room emergency filtration system in the isolation mode of operation within one hour.

ACTION 74 -

With one of the required monitors in a trip system inoperable, l

a.

place the inoperable channel in the downscale tripped condition within one hour.

With two of the required monitors in a trip system inoperable, b.

isolate the containment and drywell purge and vent penetrations i

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' ACTION 75 With one of the required monitors in a trip system inoperable, a.

place the inoperable channel in the downscale tripped condition i

within one hour.

b.

With two of the required monitors in a trip system inoperable, 4flitiete-and-maintain-operstien ef et least eae stency ge; treets. eat assyste;;; ithin 12 h;;-..

e st a bt.sk SE CcND A RY E

CO NTA I N M ENT INTEc3RIT(

w.4 h at least-

.e s4 and by w.4 %.

12 howrs.

7 4,e.4 ment ~ subsy s tem o pera+ in3 3 as l

l GRAND GULF-UNIT 1 3/4 3-58 Ametidment No. _. Order APR 1 a tom l

s INSTRUMENTATI0ft METEOROLCGICAL MC;i!TORING IMSTRUMENTATICH LIMITING C0t:DITIO!! FOR 03ERATION 3.3.7.3 The meteorological mer.itoring instrumentation channels snown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

required a.

With one or more meteorological monitoring instrumentation channels l 348 3

incperable for more than 7 days, in lieu of any other report required by Specification 6.9.1, prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not aoplicable.

SURVEILLANLE REQUIREMENTS 4.3.7.3 Each of the above recuired meteorological monitoring instru=entation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK l

and CHANNEL CALIBRATION cperations at the frequencies shown in Table 4.3.7.3-1.

e P

m.

6 GRAND GULF-UNIT 1 3/4 3-53 Amendment No. __.

l

-. ~

INSTRUMENTATION RADIOACTIVE LICUID EFFLupjT MONITORING INSTRUMENTATION

~

LIMITING CONDITICN For. C?ERATION 3.3.7.11 The radicactive liquid ef fluent monitoring instrumentation channels shown in Table 3.3.7.11-1. hall be OPERA 3LE with their alarm / trip setpoints set to ensure th:. tr.e licit: of Speci: cation 3.11.1.1 are not exceeced.

The alarm / trip setpoints cf :not2 chann.t s shall be determined in accordance with i

Cff:it:

thejOffSITC DOSE C&CUu T!OA/MpAfukLD :

-C ':.?;t:;

"cr.;;' (ODCM).

0o y

APPLICABILITY:

At all times.

ACTION:

I a.

With a re.diocct'et liquid eff*.uent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification. <amadiately suspend the release of radioactive liquid i

effluent > mea'tsred by the affected channel or declare the channel inoperacia.

b.

With less than :!.e ci.aimur. nuiber of radioactive liquid effluent monitori.g ins ruceatation chtnnels OPERABLE, take the ACTION shown in Tatic 3.3.7.11-1.

F. ester? the inoperabia instrumentation to CPERAELE statu.s w; thin the tite specified in the ACTION explain l%

why tais ino.:e-abilit, was ne: correctec in a timely nner in the o'

next der $4nnui. sedisacti.s Effluent Release Report.

andjif un&Uccessfuh,

c.

The provisions or Specifiesti:ns 3.0.3, 3.0.4 and 6.9.1.11 are not applicatie.

I i

SURVEILLANCE RECU*REMENTS 1.3.7.11 Each ra-aloactive liquid eff1'Je,t monitoring instrumentation channel

~

shall be demons;"ated OPE?ASLE by perfor nance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL PJNCTIONAL TEST operations at the 1'requencies shown in Table 4.3.7.11-1.

l t

l i

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Amendment Mo.

GRAND GULF-UNIT 1 3/4 3-82

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l GRAND GULF-UNIT 1 3/4 3-83 Amendment No.

l

L (1F-r l

J L

JZ i

m W o >=

E - 66 m

w-

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th

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GRAND GULF-UNIT 1 3/4 3-85 Amendment No. 7, - -.=

_-..-,..,-...n.,,.-

-.,. -,. -.- ----_,- ~_.-_

4..,-.,,-----v,,.n.,,-,,

. n INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.12-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limit of Specification 3.11.2.1*are not eiceeded.

The alarm / trip setpoints ofa//ceJ/eth:::-channels shall be determined in accordance with the ODCM.

aff APPLICABILITY:

As shown in Table 3.3.7.12-1 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected chanael or declare the channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.12-1.

Restore the inoperrble instrumentation to g;

OPERABLE status within the time specified in the ACTION ec gxplain l(3i why this inoperability was not corrected in a timely manner \\in the next Semiannual Radioactive Effluent Release Report.fandy unsuccessfuI, \\

c.

The provisions of Specifications 3.0.3, 3.0.4 and 6.9.1.11 are not applicable.

SURVEILLANCE REOUIREMENTS i

4.2.7.12 Each radioactive gaseous effluent monitoring instrumentation channel l

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.

i l

l i

See Spec lC 'c a +lon 3.1l. 2.6 'a nd 3,II.2. 7 for ' the Explosive Ga.s 9

%nIhr and Off as fretten++eret A1 nob r lionits.

b' 4

GRAND GULF-UNIT 1 3/4 3-87 A,,,chent No. -

j-9 TABLE 3.3.7.12-1 (Continued)

RA010ACII/E GASEOUS EFFLUENT MONITORING INSTRUMENTATION ii MINIMUM CHANNELS OPERABLE APPLICABILITY Acil0N

~

INSTRUMENT 6.

OFFGAS PRE-TREATMENT MONITOR 126 Noble Gas Activity Monitor 1

a.

7.

OFFGAS POST-TREATMENT MONITOR

' Noble Gas Activity Monitor

(

a.

Providing Alarm and Automatic 121 1

Termination of Release h

8.

SrAdD6 Y gas TAEAnmaar Ernsi-

,]

maastogry&. SYSTEM LA*6)

A.

i

)

n.

,m

~.a.o. t-w i n n.>.c uis,se,

1 y

G>

s

~

N I

+

h D

t

l l

l TABLE 3.3.7.12-1 (Continued)

~

l RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION At all times.

I During 'ain, condenser offgas treatment system operation.

l C*

m During operation of the main condenser air ejector.

ACTION 121 -

With the number of channels OPERABLE less than required by the l

Minmum Channels OPERABLE requirement, effluent releases via this i

pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are l

~

analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the number of channels OPERABLE less than required by the ACTION 122 -

Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required by Table 4.11.2.1.2-1.

With the number of channels OPERABLE less than required by the ACTION 123 -

Minimum Channels OPERABLE requirement, effluent release via this j

pathway may continue for up to 30 days grovided the flow rate is estimated at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .)

ACTION 124 -

With the number of channels OPERABLE less than required by the l

Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue for up to 30 days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

t ACTION 125 -

[ DELETED]

l L

With the number of channels OPERABLE less than required by the

}

l l

ACTION 126 -

r Minimum Channels OPERABLE requirement, the SJAE effluent may be l

released to the environment for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

i The offgas system is not, bypassed, except for filtration a.

system bypass during plant startu'ps, and b.

The offgas delay system noble gas activity effluent downstream monitor is OPERABLE; i

SHUTDOWN Otherwise, be in at least HOT SFANOBP within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sf and s,u w,

CbLD SHUThoWN svlthln the follow lo,3 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , Rj A

(

4C7:o4 8A 1 - (235KAT-j i

I k nde nt No. 7, _

GRAND GULF-UNIT 1 3/4 3-91 l

~

Insert for Table 3.3.7.12-1 Page 3/4 3-91 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

O

i, e

1 TA8tE 4.3.7.12-1 I

h RADIDACTIVE GASE0US I FFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREENTS

,z, CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE iQ CHECK CitECK CAllBRATION TEST REQUIRED lE INSTRUNENT

>i id 1.

RADWASTE BUILDING VENTILATION

<M MONITORING SYSTEM l

a.

Noble Gas Activity Monitor -

J Providing Alarm D

M A(3)

Q(2)

I I

b.

Iodine Sampler W

N.A.

i c.

Particulate Sampler W

N.A.

M.A.

N.A.

l l/2.2 d.

Flow Rate Monttor D

N.A.

R Q (S) w 8

IN Sampler Flow Rate Monitor D

N.A.

R N.A.

'w e.

i *"

j 2.

MAIN CONDENSER OFFGAS TREATMENT i

SYSTEN EXPLOSIVE GAS MONITORING SYSTEN

]

D N.A.

Q(4)

M s.

Hydrogen Monitor 3.

CONTAINMENT VENTILATION MONITORING SYSTEM Noble Gas Activity Monitor D

M A(3)

Q(2) a.

Providing Alarm I

W N.A.

N.A.

3a b.

Iodine Sampler 3

i b

c.

Particulate Sampler W

N.A.

i f

R l122.

$A d.

Effluent System Flow Rate D

N.A.

R Q (5)

R Monitor Sampler Flow Rate Monitor D

N.A.

R N.A.

P l

e.

TABLE 4.3.7.12-1 (Continued)

Rt.310 ACTIVE GASE0ils EFFLUENT MONITORING INSTRWENTATION SURVEILLANCE REQUIREMENTS O

oCG CHANNEL MODES IN WlICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE c

~

INSTRUMENT CHECK CllECK CAllBRATION TEST REQUIRED 4.

TUR8INE BLOG. VENTILATION MONITORING SYSTEM a.

Noble Gas Activity Monitor 0

M A(3)

Q(2) b.

Iodine Sampler W

N.A.

[

i c.

Particulate Sampler W

N.A.

M.A.

l122 w

d.

Flow Rate Monitor 0

N.A.

R Q(5) 5 Sampler Flow Rate Monitor 0

N.A.

R N.A.

w e.

O 5.

FUEL HANDLING AREA VENTILATION MONTORING SYSTEM a.

Noble Gas Activity Monitor D

M A(3)

Q(2) b.

Iodine Sampler W

N.A.

c.

Particulate Sampler W.

N.A.

12 2 d.

Flow Rate Monitor D

N.A.

R Q (5)

Sampler Flow Rate Monitor 0

N.A.

R N.A.

{

e.

[

o6

. v*

I

~ -..

r TABLE 4.3.7.L2-1 (Continued)

RAOlhACTIVE'GASEtiEFFLUENTMONITORit,INSTRUMENTATIONSURVEILLANCEREQUIREMENTS S

Q CHAI!NEL MODES IN WHICH E

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE 5.

INSTRUMENT CllECK CHECK CALIBRATION TEST

' REQUIRED

-4 6.

OFFGAS PRE-TREATMENT MDMITOR s.

Noble Gas Activity Monitor D

M A(3)

Q(2) 7.

OFFGAS POST-TREATMENT MONITOR a.

Noble Gas Activity Monitor Providing Alarm and Auto-matic Termination of Release D

M A(3),,

Q(1) g i

i T

8.

n** M y &*s n e m ' a s w "

,a Mo*.TOA.WG. S)fSTEm (A s B )

?

n. deale. Ga. N v.43 h. fe D

m 40)

@U 7

I a.

k 4

l' l

e

=a

~ '4 G

2' O

9

~

TABLE 4.3.7.12-(Continued)

J RADI0 ACTIVE GASEOUS EFFLUENT MONITORING

)

INSTRUMENTATION SURVEILLANCE REQUIREMEhTS TABLE NOTATION.

At all times.

During main condenser offgas treatment system operation.

i During operation of the main condenser air ejector.

l

SOURCE CHECK say be deferred to the next shutdown of greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months duration if unable to be performed at the monthly interval due to j

inaccessibility because of being in a high radiation area.

" The sensor will be calibrated for ar/hr or cpe from the calibrat.fon standard.

The conversion to release rate will be performed during subsequent unit opera-i

)

tion, but within one week.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation (1) of this pathway and control room alars annunciation occurs if any of the j

following conditions exists:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

l 2.

Circuit failure.

1 i

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demor. strate that control room alar annuciation occurs if any of the following conditions exists:

1.

Instrument indicates measured lev 61s above the alars setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

Instrument controls not set in operate mode, The initial CHANNEL CALIBRATION shall be performed using one or more of r

i (3) the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in sensurement assurance activities with NBS. These standards shall permit calibrating the system over its intended measurement range.

For subsequent i

CHANNEL CA1IBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples i

containing a nominal:

1.

One volume percent hydrogen, balance nitrogen, and 2.

Four volume percent hydrogen, balance nitrogen.

(5) Compare the measured flowre.te to the expected design howrate 12 2 for exishg plant con &*tions, GRAND GULF-UNIT 1 3/4 3-95 Amendment No. 8

CONTAINMENT SYSTEMS

(

STANDBY GAS TREATMENT SYSTEM.

~

LIMITING CONDITION FOR OPERATION 3.6.6.3 Two independent standby gas treatment subsystems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and *.

ACTION:

~~

With one standby gas treatment subsystem inoperable, restore the a.

inoperable subsystem to OPERABLE status within 7 days, or:-

1.

In OPERATIONAL CONDITION 1, 2 or 3, 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 SHUTDOWN within the following J

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

, suspend handling of irradiated fuel" 2.

In Operational Condition in the primary or secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

b.

With both standby gas treatment subsystems inoperable in Operational h.

Condition *,, suspend handling of irradiated fuel in the primary or secondary containment, CORE ALTERATIONS or operations with 'a potential for draining the reactor vessel. The provisions of Specification 3.0.3.

are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.6.3 Each standby gas treatment subsystem shall be demonstrated OPERABLE:

At least once per 31 days by initiating, from the control room, flow a

through the HEPA filters and charcoal adsorbers and verifying that j

the subsystem operates for at least 10, hours with the heaters

~

o

, OPERABLE.

L co,,Woous "When irradiated fuel is being handled in the primary or secondary containment, and during CORE ALTERATIONS and operations with a potential for draining the,,

reactor vessel.

GRAND GULF-UNIT 1 3/4 6-53 Amendment No. 9 3 _

i

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FICTRATION SYSTEM i

LIMITING CONDITION FOR OPERATION 3.7.2 Two independent control room emergency filtration system subsystems shall i

be OPERABLE.

APPLICABILITY: All OPERATIONAL CONDITIONS and *.

ACTION:

In OPERATIONAL CONDITION 1, 2 or 3 with one control room emergency 1

a.

filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 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 SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

t b.

In OPERATIONAL CONDITION 4, 5 or *:

1.

With one control room emergency filtration subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the isolation mode of operation.

With both control room emergency filtration subsystems inoperable, j

2.

suspend CORE ALTERATIONS, handling of irradiated fuel in the

' fy primary or secondary containment and operations with a potential Q

for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable in c.

Operational Condition *.

l SURVEILLANCE REQUIREMENTS i

I Each control room emergency filtration subsystem shall be demonstrated 4.7.2 OPERABLE:

i At least once per 31 days on a STAGGERED TEST BASIS by initiating, a.

from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least l

10ghours with the heaters OPERABLE.

j L eonuvous At least once per 18 months or (1) after any structural maintenance b.

on the HEPA filter or charcoal adsorber housings, or (2) following I

i painting, fire or chemical release in any ventilation zone a

.e communicating with the subsyster, by:-

o 1.

[ DELETED) 1 When irradiated fuel is being handled in the primary or secondary containment.

i P

GRAND GULF-UNIT 1 3/4 7-5 Amendment No. 7, 9 -

3

,_.,-...._-..,.,.n.--

y.

TABLE 4.11.2.1.2-1 RADIDACTIVE' GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Lim Ga ous Release Sampling Analysis Activity of Dete ion Type Frequency Frequency Analysis (L )

(p /ml)"

i D

b

~4 A. Contai nt M

M Principa} Gamma 1x10 Ventilati Grab Sample Emitters j

/

Exhaust

-6 H-3 1x10

~4 a

1x10 ers} Gamma l-b b

B. Turbine Building M

l g

Princ Ventilation Grab Sample Emi Exhaust

-6 3

1x10

~4 1x10 C. Offgas Post Treatment M

M Principa, Gamma Emitters Exhaust, whenever Grab Sam e there is flow l

-12 f

D. (1) Radwaste Building.

Continuous y

I-131 1x10 CD d

e r0 cal

-10

[Cha Ventilation Samp1 1-133 1x10 t

g l

Exhaust

-11 d

e 1x10 (2) Fuel Handling Conti ous y

Principa} Gamma Area Ventila-Particulate Emitters tion Exhaust Sample 1-131,Others) i

-11

[ Continuous d

M Gro Alpha 1x10 l

(3) Containment l

Ventilation Composite Particulate l

Exhaust Sample (4) Turbine uilding Continuous Q

Sr-89, Sr-90 1x10~11 d

Composita l

Venti tion Particulate l

Exh st Sample

~

Continuous Noble Gas Noble Gases 1x i

Monitor Gross Beta l

or Gamma l

GRAND GULF-UNIT 1 3/4 11-9

c-i TABLE 4.11. 2.1. 2-1 RADICACTIVE' GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM

~

t Minimum Type of Lower Limit l

Gnscous Release Sampling Analysis Activity of Detection Typ3 Frequency Frcquency Analysis (LLD) l (pC1/al)"

l

-4 A. (1) Radwaste Building' M

M Principal Gamma 1x10 I

Ventilation Grab Sceple Emitters

l 6

Exhaust r

-6 i

H-3 1x10 (2) Fuel Handling i

Area Ventila-d

/

I-131 1x10'U tion Exhaust Continuous Charcoal f

Samp e I-3 h10 (3) Containment I

Ventilation d

/

Principa} Gamma 1x10 "-

l Exhaust Continuous Particulata Emittars Sample (1-131, others)

(4) Turbine Building d

-n Ventilation Cont'indous M

Gross Alpha 1x10 co !

Exhaust Composita

<0 l Particulata Sample 4

d

-11 Continuous Q

Sr-89, Sr-90 1x10 Composita i

Particulata Sample I

Continuous Noble Gas Noble Gases 1x10

[

~0 Monitor Gross Beta l

i or Gamma BI0ffgasPostTreatment

'M M

Principa}Ga.ma 1x16 Exhaust, whenever Grab Sample Emitters i

l there is flow o

tr) s e o s -. T..

. e A t= % st, wk.+=*ec N,

3 were.. fi..

@l m swai c.. rr. 4 e*

q-s E,k.a.,.k.

e t u r.

a (i. w I

l GRAND GULF-UNIT 1 3 /1 * ~.-9 Amendment No.

t r

TABLE 4.11.2.1.2-1 (Continued)

I RADIOACTIVE GASEOUS WASTE S'AMPLING AND ANALYSIS PROGRAM r

TABLE NOTATION (Continued) j Analyses shall also be performed following startup from cold shutdown, or b.

i a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER lNg withinaonehourperiod.g i

Samples shall be changed at least once per 7 days and analyses shall be j

completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

c.

Sampling and analyses shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

for at least 7 days following each shutdown, startup or THERMAL POWER y

change exceeding 15 percent of RATED THERMAL POWER in one hour., When s.

samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may lN G) c be increased by a factor of 10 6

o The ratio of the sample flow rate to the sampled stream flow rate shall l

d.

be known for the time period covered by each dose or dose rate calculation i

made in accordance with Specifications 3.11.2.1 and 3.11.2.3.

The principal gamma emitters for which the LLD specification applies Kr-87, Kr-88, Xe-133, e.

exclusively are the following radionuclides:

Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for 4

This list does not mean that only these nuclides l

particulate emissions.

Other peaks which are measurable and I

are to be detected and reported.

i j'

identifiable, together with the above nuclides, shall also be identified and reported.

1 l

l l

"For a more complete discussion of the LLD, and other detection limits, see l

the following:

l HASL Procedures Manual, HASL-300 (revised annually).

(1)

Currie, L. A., " Limits for Qualitative Detection and-Quantitative (2)

Determination - Application to Radiochemistry" Anal. Chem. 40, Hartwell, J. K., " Detection Limits for Radioisotopic Counting Tecnhiques,"

586-93 (1968).

j Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).

(3) i i

i i

f 1

1 i

Amendment No,

-- ~.

/4 11 11 3

a nann GutF-UNIT C

Insert to Table 4.11.2.1.2-1 Notations b and c. Page 3/4 11-11 This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

I i

I 2

265sd15

e,. :

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE l

LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.

~

APPLICABILITY: - At all tima. Whenever -tAe main condenser afg as q

ACTION:

treatment sy. stern ss s'n opetation.

O'

^

With the concentration of hydrogen in the main condenser'offgas a.

treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

The provisions of Specifications 3.0.3, 3.0.4 and 6.9.1.11 are not applicable.

SURVEILLANCE REOUIREMENTS mun%e'n3 r

4.11.2.6 Theconcentrationofhydrogeninthemaincondensegroffgastreatment

=4a+=4

'-- the system shall be determined to be within the above limits by waste gas in the main condenser off gas treatment system with the hydrogen monitor OPERABLE as required by Table 3.3.7.12-1 of Specification 3.3.7.12.

l l

\\

j l

(

f

(

l L

GRAND GULF-UNIT 1 3/4 11-16 Anrendmed Md -

Y Z

e f

. r i

RADI0 ACTIVE EFFLUENTS t

MAIN CONDENSER '

j 7

I LIMITING CONDITION FOR OPERATION l

3.11.2.7 The gross radioactivity (gamma) rate of the noble gase Xe-1252, y

":-133r-Xe-135r-#e*138r-Kr-45m -Mc-47r4c-88 measured at the offf gas recombiner s

e.ffluent shall be limited to less than or equal to 380 millicuries /second, l

A e w m:.t.s A v,.3 g

APPLICABILITY:

OPERATIONALCONDITIONS1,2$and3" i

t" ACTION:

gg +,,. y

)

With the gross radioactivity rate of th nogle gases X;-135, Xe-133, X:-125, Mr 130- Kr "5, Kr "7=, =d Mr 00 at thefofffgas recombiner effluent exceeding q380 mi11 curies /second,' restore the gross radioactivity release rate to within 7

its' 11mi within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT -STAN09Y-within the next i

i 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .4 in ceta myoe.M wdi, g.

l

, h,Ile. a.y "%,4 6c.4 rf.

t I # SURVEILLANCE' REQUIREMENTS

\\

s j

4.11.2.7.1 The radioactivity release rate of noble gases near the outlet of i

the main condenser air efector shall be continuously monitored in accordance i

with Specification 3.3.7.32.

red;oIs6.4 4.11.2.7.2 The gross -radoactivity release rate of the noble gases X:-135e, y

X:-132, X:-135r-Xe-138.--Kr-45m;-Kc-87, r.d -Kr"" from the main condenser air i

E efector shall be determir.e(to be within the limits of Specification 3.11.2.7

~

at the following frequencies by performing an isotopic analysis of a representative sample of gases taken at the 44+ charge (prier t: di%tien-2 l

--aM/ee-discharge)-of-the-aain cend=::r sic-eject :

c(has rew.i6irer e.WA.. +:

l

\\

f l

,a.

At least once per 31 days.

j b.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the Eendensee-g!

Mr jector-Noble-Ges-Activity Monitor, of greater than 50%, after ~

j

[

factoring.out increases due to changes in THERMAL POWER level, in l

the nominal + steady state fission gas release from the primary coolant.

l j

\\

(o%sr.w..a.,#

4 4

I

(

g M e.n 4he_, mm.se Cooktt'See ate s '5c s +o ** Is i s, er f t h + *

n.

l r%. $r.gta o+ s,,0.<w.r.c, 9.o.y a,

s, +-

v.

w4 o.;v s. u.te.

t 4

I 9

3/4 11-17 A m eid pse Wf. N o. -

l.!

GRAND GULF-UNIT 1 a x

,w_,--

.. _ ~ ~ _,. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

- - ' - ~ ~ * - ' ' ' - ' ~ ~ ~ ' '

INSTRUMFNTATiO.A i

B_ASC5

I I

3/4.3.7.11 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

.The radioactive liquid effluer.t monitoring instrumentation is*provided to' i

j

. monitor and control, as applicable, the releases of radioactive materials inThe liquid effluents during actual or potential releases of liquid effluents.

(

clara/ trip setpoints for these instruments shall be calculated in accordance with the procedures in the CDCM to ensure that the alars/ trip will occur prior j

to exceeding the limits of 10 CFR Part 20.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design l

l Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION j

3/,4.3.7.12 The radioactive gaseous affluent monitoring instrumentation is 'provided

tert:1:

to monitor and control, es applicable Se r:10::::--ef r:df::'tiv:

ef'! uerts

-$n gaseous effluents during actual or potential re13ases.W:::::

Th: :1: =/tM p-::tpeint: f:r th::: in:tr. nt: 05:11

::1:;1:t:d f

M: ::

leithth: pree:dar:: in the-90CM t: :n:gr: th:t th:

1

/tri; efl1 :::ur pH :r o

T t: :::::: h; th: li:4h-ef-10-GFA-Pert 20.

This-in:trur:nt: tier Of ;:t:ntfally l

i i

=f ter

: in t % :: : ;:: h:1du; :y:t:.

The OPERABILITY and

$ :n;1::ft:

c use of this instrumentation is consistent with the requirements of General le.

i e

Design Criteria 60, 63 ad 64 of Appendix A to 10 CFR Part 50.

H o'

A t

3/4.3.8 PLANT SYSTEMS ACTUCION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action j

to mitigate the consequences of accidents that are beyond the ability of the The LPCI mode of the RHR system is automatically initiated operator to control.

on a high drywell pressure signal and/or a low reactor water level, level 1, The containment spray system will then actuate automatically following signal.

Negative barometric pressure high drywell and high containment pressure signals. fluctuations are a

(

fied for drywell and containment pressure-high.

A 10-minute minimum, 13-minute vie'iiu.a time delay exists between initiation of LPCI and containment spray i

A high reactor water level, level 8, signal will actuate the feed-l actuation.

l water system / main turbine trip system.

l t

i 1

GRAND GULF-UNIT 1 3 3/4 3-6 Amendment No.

[

- t.

o Insert to Bases 3/4.3.7.12, Page B 3/4 3-6 Those instruments that monitor the activity of gaseous effluents being released to the environment shall have their alarm / trip setpoints calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

Other instruments that monitor offgas processing, (i.e., the Explosive Gas Monitor Offgas Pre-Treatment Monitor, and Offgas Post-Treatment Monitor) are calibrated according to plant procedures.

t a

cnwm

CONTAINMENT SYSTEMS BASES DRYWELL POST-LOCA VACU M BREAKERS (Continued)

~

drywell purge system, is necessary to insure that the post-LOCA dr concentration does not exceed 4% by volume.

Fo11cwing vacuum relief, the drywell purge system pressurizes the forcing noncondensibles through the horizontal vents and into the cont concentration below the fiammable limits.

at a rate designed to maintain the Ha There are two 100% vacuum relief systems so that the plant may cont operation with one system out of service for c limited period of time.

SECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level, 3/4.6.6 radioactive material which may result from an accident.an When the reactor is in COLD when the containment is sealed and in service.d the Auxiliary Building

,qT00WN or REFUELING, the containment may be open an and Enclosure Building then become the only containment.

SH dampers / valves are the times used in the FS For automatic isolation valves not l

valves with analytical closing times.

having analytical closing times, closing times i

i Maximum closing times for these valves was determined by using a

) ASME times the allowable ((fom previous test closure to next test closure Section XI margin and-adding this to the previous test closure time,

[

l Establishing and maintaining a vacuum in the Auxiliary Building an Enclosure Building with the standby gas treatment system once p along with the surveillance of the doors,. latches, dampers and j

d y i

quate to ensure that there are no violations of the integrity of the CmhNuoa.s contnineent The OPERABILITY of the standby gas t eatment systems enfures t

!"fficient iodine removal capability will be available The reduction in containment ioding.inve tory reduces the resultin containment leakage.

The operation boundary radiation doses associated witofthissystemandres i

h y

C; m ti c operation of the system assumptions used in the LOCA analyses.

fficient to with the heaters OPERABLE for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is su reduce the buildup of moisture on the absorbers and HEPA filters.

Gas Treatment System heaters is performed 75 f Section 14.2.3.

with the exception of the 5% current phase balance criteria o The offsite power system for the Grand Gulf Nuclear St transpositional 500 KV grid.

Voltage unbalances bution which results in unbalanced voltages in the plant. criteria are exceeding the ANSI N510-1975 5%

9 Insert w AmendmentNo.9,_[

6 3/4 6-6 GRAND GULF-UNIT 1

M:

.. ~. ~... -.

.. o l

Insert for Bases 3/4.6.6, Page B 3/4 6-6 For painting, fire, and chemical releases other than carbon dioxide in any ventilation zone communicating with the standby gas treatment system, the Surveillance Requirements are adequate to ensure charcoal adsorbency is maintained. A release of carbon dioxide for any reason other than a fire will not adversely af fect the charcoal's adsorbency and the Surveillance -

Requirement need not be performed.

i P

l 265sdl7

w 3/4.7 PLANT SYSTEMS BASES SERVICE WATER SYSTEMS 3/4.7.1The OPERABILITY of the service water systems ensures that sufficient c capacity is available for continued operation of safety-related equip normal and accident conditions. assuming a single failure, is consistent w conditions within acceptable limits.

donnNWOus -

CONTROL ROOM EMERGENCY FILTRATION SYSTEM f

3/4.7.2 The OPERABILITY of the, control room emergency fi tration system ensures l

ions personnel during lg that the control room will remain habitable for oper -Cahthe operation of -

g and following all design basis accident conditions.

i the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filten The OPERABILITY of this system in conjunction with control room design i

1r based on limiting the radiation exposure to perscnnel occupying the con This limitation is con-room to 5 rem or less whole body, or its equivalent.sistent with "A",

i-i i

f 10 CFR Part 50.

The surveillance testing for verifying heat dissipation for the Control l

Room Emergency Filtration System heaters is performed in accordance wl with the exception of the 5% current phase balance criteria of Sec-The offsite power system for the Grand Gulf Nuclear Station N510-1975 l

The gr.id has an inherent l

tion 14.2.3.

consists of a non-transpositional 500 KV grid. unbalanced load criteria are not atypical.

l Voltage unbalances exceeding the ANSI N510-1975 5%

3/4Y7.3 REACTOR CORE ISOLATION' C00 LING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isoletion frem its primary :

sink and the loss of feedwater flow to the reactor vessel without requiring The RCIC actuation of any of the Emergency Core Cooling System equipment.

--l+- i= conservatively required to be OPERABLE when l

system provides adequate core cooling up to 225 psig.

The RCIC system specifications are applicable during OPERATION i

1, 2 and 3 when reactor vessel pressure exceed d

With the RCIC system inoperable, adequate core cooling is assured b}

~'

OPERABILITY of the HPCS system and justifies the specified 14 da The surveillance requirements provide adequate assurance that RC period.

Although all active components are testable and !.

be OPERABLE when required. full flow can be demonstrated by recircul complete functional test requires reactor shutdown.is mainta j

earliest possible moment.

Amendment No. 7, 9,_

l B 3/4 7-1 GRAND GULF-UNIT 1

r, e..,

Insert for Bases 3/4.7.2. Page B 3/4 7-1 For painting, fire, and chemical releases other than carbon dioxide in any ventilation zone communicating with the control room emergency filtration system, the Surveillance Requirements are adequate to ensure charcoal adsorbency is maintained. A release of carbon dioxide for any reason other than a fire will not adversely affect the charcoal'a adsorbency and the Surveillance Requirement need not be performed.

l

\\

l t

l l

Z65sd12

ML20092G884

Text

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