ML18051B012

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Proposed Changes to Tech Specs 1.0 & 6.0,reflecting 10CFR50.73 Reporting Requirements
ML18051B012
Person / Time
Site: Palisades Entergy icon.png
Issue date: 07/30/1984
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051B010 List:
References
NUDOCS 8408030152
Download: ML18051B012 (11)
v • d • e


Text

Consumers Power Company Palisades Plant - Docket 50-255 PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST PROPOSED PAGES

- 08030152-*840730, '._._(~--T ;\ 10 Pages

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TS0784-0022-NL02

  • .1. 4 e

MISCELLANEOUS DEFINITIONS Operable A system or component is operable.if it is capable of fulfilling its design functions.

Operating A system or component is operating if it is performing its design functions.

Control Rods All full-length shutdown and regulating rods.

Containment Integrity Containment integrity is defined to exist when all of the following are true:

a. All nonautomatic containment isolation valves and blind flanges are
  • closed.
b. The equipment door is properly closed and sealed.
c. At least one door in each personnel air lock is properly closed and sealed.
d. All automatic containment isolation valves are operable cir are locked closed.
e. The uncontrolled containment leakage satisfies Specification 4.5.1.

Dose Equivalent I-131 Dose. Equivalent I-131 shall be that concentration of I-131 (uC/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

E - Average Disintegration Energy E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (ip MEV)

  • for isotopes, other than iodines, with half lives greater than. 15
  • minutes, making up at least 95% of the total noniodine activity in the coolant.

Safety Safety as used in these Technical Specifications refers to those safety issues related to the nuclear process and, for example, does not encompass OSHA considerations.

1-4 PROPOSED TS0184-0002A-NL02

1.4 e

MISCELLANEOUS DEFINITIONS (Continued)

Reportable Event A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part SO .

1-5 PROPOSED TS0184-0003A-NL02

  • 3.1 PRIMARY COOLANT SYSTEM (Continued) 3.1.4 Maximum Primary Coolant Radioactivity Specifications
a. The specific activity of the primary coolant shall be limited to:

i) (1.0 µCi/gram dose equivalent I-131, and

2) (100/E µCi/gram.
b. With the specific activity of primary coolant > 1.0 µCi/gram dose equivalent I-131 but less than 40 µCi/gram, operation may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that operat~on under these circumstances shall not exceed 36 days per calendar year.
c. With the specific activity of the primary coolant > 1.0

µCi/gram dose equivalent I-131 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval or exceeding 40 µCi/gram, be shutdown with T (S00°F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

avg

d. With the specific activity of the primary coolant )*100/E

µCi/gram, be shutdown with Tavg ( S00°F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e. With the specific activity of the primary coolant > 1.0

µCi/gram dose equivalent I-131 or > 100/E µCi/gram, perform the sampling and analysis requirements of item 1 of Table 4.2.1 until the specific activity of the primary coolant is restored to within its limits. A Special Report shall be prepared and submitted to the Director of the appropriate Regional Office within thirty days of the occurrence of the event. This report shall contain.the results of the specific activity analyses together with the *following information:

1. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceed,
2. Fuel burnup by core region,
3. Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,
4. History of de-gassing operation, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded, and
5. The time duration when the specific activity of the primary coolant exceeded 1.0 µCi/gram dose equivalent I-131.

3-17 PROPOSED TSOS84-0001A-NL02

. ADMINISTRATIVE CONTROLS

c. Review of all proposed changes to Appendix "A" Technical Specifications.
d. Review of-all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
e. Investigation of all violations of the Technic.al Specifications. (A report shall be prepared covering evaluation and recommendatio~s to prevent recurrence and forwarded to the Vice President - Nuclear Operations and to the Executive Engineer - NAPO.)
f. Review of plant operations to detect potential nuclear safety hazards.
g. Performance of special reviews and investigations and reports thereof as requested by the Plant General Manager or Chairman of NSB.
h. Review of the Site Emergency Plan and implementing procedures.
i. Review of all reportable events as defined in Section 1.4.

6.5.1.7 AUTHORITY The PRC shall:

a. Recommend in writing to the Plant General Manager approval or disapproval of items considered under Specifications 6.5.1.6.a. through d. ~bove.
b. Render deter~ination~ in writing with regard to whether or not each item considered under Specificationi 6.5.1.6.a. through e. above constitutes ~n

- unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Operations and to the Vice Chairman of NSB of any disagreement between the PRC arid the Plant General Manager; however, the Plant General Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.i.1 above.

RECORDS 6.5.1.8 The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSB.

6.5.2 NUCLEAR SAFETY BOARD (NSB)

RESPONSIBILITIES 6.5.2.1 The Nuclear Safety Board (NSB) is responsible for maintaining a cOntinuing examination of nuclear safety--rela'ted Corporate and p1ant activities and defining opportuni-ties for policy changes related to improved nuclear safety performance. The NSB shall operate in accordance with a written charter, approved by the Vice President - Nuclear Oper-ations, which designates the membership, authority, and rules for conducting the meetings.

FUNCTION 6.5.2.2 The NSB shall function to provide review of designated activities in the areas specified in Specification 6.5.2.3.

nu0283-0452a-43-142 Proposed

ADMINISTRATIVE CONTROLS QUORUM 6.5.2.7 A_quorum of-NSB shall consist of -the Chairman arid four (4) members. - (The ViCe- --------

Chairman may be a voting member when not acting in the capacity of Chairman.) No more than a minority of the quorum shall have line responsibility for operation of the facility. It is the responsibility of the Chairman to ensure that the quorum convened for a meeting contains appropriately qualified members or has at its disposal consultants sufficient to carry out the review functions required by the meeting agenda.

6.5.2.8 RESPONSIBILITIES REVIEW 6.5.2.8.1 NSB shall be responsible for the review of:

  • a. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
b. All reportable events and other violations (of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements or of internal procedures or instructions) having nuclear safety significance.
c. Issues of safety significance identified by t&e Plant General Manager~ the NSB Chairman, Executive Engineer - NAPO or the PRC.
d. Propos*ed changes in the operating license or Appendix "A" Technical Speci-:

fications.

e .. The results of actions taken to correct deficiencies identified by-the audit program specified in Specification 6.5.2.8.2 at least once every six months.

f. Safety evaluations for changes to procedures, equipment, or systems and tests or experiments completed under the provisions of 10 CFR 50.59; to verify that such actions did not constitute an unreviewed safety question.
g.
  • Maintain cognizance of PRC activities through NAPO attendance at scheduled PRC meetings or through review of PRC meeting minutes.

AUDITS 6.5.2.8.2

  • Audits of operational nuclear safety-related facility activities shall be performed under the cognizance of NSB. These audits shall encompass:
a. The conformance of plant operation to provisions contained within' the Technical.Specifications and applicable license conditions at least once per 12 months.
b. The performance, training and qualifications of the entire facility staff at least once per 12 months.

rtu0283-0452a-43-42 6-8 Proposed

c. Monthiy Operating Report - Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, US Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Office to arrive no later than the fifteenth of each month following the calendar month covered by the report.

6.9.2. Reportable Events The Commission shall be notified of Reportable Events and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part SO.

6-12 PROPOSED TSOS84-0001B-NL02

6.9.2.a (DELETED) 6-14 PROPOSED TS0784-0022-NL02

6.9.2.a (Continued) (DELETED) 6-15 PROPOSED TS0184-0022-NL02

6.9.2.b (DELETED) 6-16 PROPOSED TS0784-0022-NL02

~~' ..:

~ 6.9.3.3 Special Report~

a. Special reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable referenced specification:

Specifitation Area Reference Prestressing, Anchorage, 4.5.4 90 Days After Liner and Penetration 4.5.5 Completion of Tests* Test*

Primary System Surveillance 4.3 Five Years Evaluation and Review

  • A test is considered to be complete after all associated mechanical, chemical etc., tests have been completed.
b. Bimonthly status reports on th~ program to improve the reliability of the paths to prevent post-LOCA boron precipitation shall be submitted to the Division of Operating Reactors until completed.
c. (Deleted) 6.10 Record Retention (Record not previously required to be retained shall be retained as required below commencing with the effective date of Technical Specification Change No 20. A system for efficient record retrieval shall be in effort not later than June 1976.)

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.
b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c.

d.

All reportable events as-defined in Section 1.4.

Records of surveillance activities, inspections and I

calibrations required by these Technical Specifications.

6-26 PROPOSED TS0784-0022A-NL02

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